SPECIAL REPORT ON THE OCCASION
OF THE 30TH ANNIVERSARY
OF THE JAPAN/U.S. FUSION RESEARCH COLLABORATIONJPN/US

Summar y Repor t for the Period 2001-2010

FUSION RESEARCH COLLABORATION

Japan/U.S. Coordinating Commit tee on Fusion Energy

The Japan-US Coordinating Committee on Fusion Energy (CCFE) is responsible for this report.
This report was prepared for the CCFE by four editors: Stanley L. Milora (Oak Ridge National
Laboratory), Takahisa Ozeki (Japan Atomic Energy Agency), Shigeru Sudo (National Institutefor Fusion Science), and James W. Van Dam (University of Texas at Austin). The editors
solicited written input from key persons in various fields and categories of the US-Japan fusion
research collaboration activities.
The printed version of this report is published by the Ministry of Education, Culture, Sports,
Science & Technology and the National Institute for Fusion Science, as agreed by the CCFE.
The web version of this report is published by several key organizations in the US and Japan.

SPECIAL REPORT ON THE OCCASION OF
THE 30TH ANNIVERSARY OF THE
JAPAN/U.S. FUSION RESEARCHCOLLABORATION(Summary Report for the Period 2001-2010)

March 2011

Japan/U.S. Coordinating Committee on Fusion Energy

Preface
The Japan-US Coordinating Committee for Fusion Energy (CCFE) marked its 30th anniversary in2010. The historical 30th meeting of the CCFE was held in Korea on October 13, 2010, on theoccasion of the IAEA Fusion Energy Conference. Such a long-term cooperative relationship could
not have been developed simply by the government officials in Japan and the United States ofAmerica (US), and therefore we are grateful that so many researchers made contributions tomaintain this relationship.
The history of Japan and US collaboration dates back to the discussions between Prime Minister
Fukuda and President Carter in 1977 on a new Japan and US collaboration on fusion. Based on this,a governmental agreement on Japan and US Joint Activity in the field of fusion research anddevelopment was established, and the CCFE was established in August 1979. Since then, Joint
Activity has been continued steadily for many years. We highly value the collaboration in fusion
research carried out between Japan and US in the past, and we would like to ensure the continuationof steady collaboration in the future.
Fusion power can be a very attractive energy source because of its almost inexhaustible fuelresources, high degree of safety, and low burden on the environment. Since the first fusion-related
research for energy commenced in the 1950s, considerable progress has been made worldwide. The
collaboration between Japan and US has contributed much to this progress. Based on successful
research results, the ITER Project for fusion burning experiments was initiated and is now going
forward with the cooperation of seven Parties: China, the European Union, India, Japan, Korea,
Russia and US. In order to develop an economically attractive fusion reactor, however, many
research fields still need to be studied intensively in addition to the ITER activities. These include
high beta steady-state operation, tritium breeding systems, development of material science, and soon. Japan and US have experimental devices that are suited to such research fields, and therefore,
our collaboration should be further strengthened.
The 20th Anniversary report was published ten years ago, and so this 30th Anniversary reportmainly describes the activities and highlighted results during the past decade to the present. We hopethat this report will prove useful in reviewing the long-lasting Japan and US Joint Activity, and that
it will contribute to the further development of the Japan and US Joint Activity in the future.

KATAOKA Hiroshi
Director
International Nuclear and Fusion Energy Affairs Division
Research and Development Bureau
Ministry of Education, Culture, Sports, Science and Technology
Japan

Edmund SYNAKOWSKI
Associate Director for Fusion Energy Sciences
Office of Science
Department of Energy
United States of AmericaiCONTENTS
Preface
CHAPTER 1

Introduction ......................................................................................... 1

CHAPTER 2 Fusion Technology Planning Committee (FTPC)
2.1 Objectives ................................................................................................................ 3
2.2 Activities .................................................................................................................. 3
2.3 Administration ........................................................................................................ 3
2.4 Accomplishments .................................................................................................... 4
2.4.1 Superconducting Magnets .................................................................................. 4
2.4.2 Structural Materials ........................................................................................... 5
2.4.3 Plasma Heating Related Technologies .............................................................. 5
2.4.4 Blankets ................................................................................................................ 6
2.4.5 In-Vessel/High Heat Flux Materials and Components .................................... 7
2.4.6 Others ................................................................................................................... 8
2.5 Highlights ................................................................................................................ 9
CHAPTER 3 Fusion Physics Planning Committee (FPPC)
3.1 Objectives .............................................................................................................. 21
3.2 Activities ................................................................................................................ 21
3.3 Administration ...................................................................................................... 21
3.4 Accomplishments and Highlights........................................................................ 22
3.4.1 Steady-State Operation..................................................................................... 22
3.4.2 MHD and High Beta ......................................................................................... 27
3.4.3 Confinement ...................................................................................................... 31
3.4.4 Diagnostics ......................................................................................................... 37
3.4.5 High Energy Density Science ........................................................................... 46
CHAPTER 4 Joint Institute for Fusion Theory (JIFT)
4.1 Objectives .............................................................................................................. 55
4.2 Activities ................................................................................................................ 55
4.3 Administration ...................................................................................................... 57
4.4 Accomplishments and Highlights........................................................................ 58

CHAPTER 5JUPITER-II࣭TITAN

5.1 Progress in US-Japan collaboration research.................................................... 75
5.2 Objectives, research subjects and facilities ........................................................ 75
5.2.1 JUPITER-II project (FY2001-2006)................................................................ 75
5.2.2 TITAN project (FY2007-2012) ........................................................................ 76
5.3 Administration ...................................................................................................... 79
5.4 Accomplishments and Highlights........................................................................ 80
5.4.1 JUPITER-II ....................................................................................................... 80
5.4.2 TITAN ................................................................................................................ 86
CHAPTER 6 DIII-D
6.1 Objectives .............................................................................................................. 95
6.2 Activities ................................................................................................................ 95
6.3 Administration ...................................................................................................... 95
6.4 Accomplishments and Highlights........................................................................ 95
CHAPTER 7 HFIR
7.1 Objectives ............................................................................................................ 103
7.2 Activities .............................................................................................................. 103
7.3 Administration .................................................................................................... 104
7.4 Accomplishments and Highlights...................................................................... 104
CHAPTER 8 Fusion Archives Activity
8.1 Objectives ............................................................................................................ 117
8.2 Administration .................................................................................................... 117
8.3 Summary of Activities ........................................................................................ 117
CHAPTER 9 Safety Monitoring Activities
9.1 Background and Objectives .............................................................................. 121
9.2 Summary of JWG Activities .............................................................................. 121
Appendix A List of Published Papers ................................................................... A-1
Appendix B Statistics and Related Documents
B.1 Workshop & Personnel....................................................................... A-95
B.2 Table of Safety Trips ........................................................................... A-97

CHAPTER 1

Introduction

The highest coordinating committee for the Japan/US Joint Activity in the field of fusion research is
the Coordinating Committee for Fusion Energy (CCFE), which was established in August 1979.
Since then, the Joint Activity has been continued for many years to the present. The historical 30th
meeting of the CCFE was held in Korea on October 13, 2010. Immediately following this CCFE
meeting, a memorable 30th Anniversary Celebration was held, and the Co-Chairpersons from both
Japan and US gave congratulatory speeches.
The organizational configuration of the Japan/US Joint Activity is shown in the figure below. The
Executive Secretaries Meeting (ESM) is for the purpose of preparation work for CCFE. The researchareas represented by Fusion Technology Planning Committee (FTPC), Fusion Physics Planning
Committee (FPPC), Joint Institute for Fusion Theory (JIFT), TITAN project, Doublet III, and HFIR
submit the exchange activity results of the current year and the proposals for the next fiscal year to
the ESM. Each research area is overseen by a Steering Committee that consists of Japanese and US
representatives.
Also, Safety Inspection Trips are conducted once every two years. An inspection team from Japanvisits experimental facilities in the US, after which the US – Japan Safety Monitor Joint Working
Group issues a report about safety, which includes suggestions for improving the safety conditionsof the facilities. Then, two years later, an inspection team from the US visits facilities of Japan. Thisroutine has been carried out 13 times. These safety trip activities have contributed much to the safetyof the collaborations.

Organization for Joint Activity
CCFE (Coordinating Committee for Fusion Energy)
ESM (Executive Secretary Meeting) by MEXT and DoE
Domestic Steering Committee (Japan)
JSPS for Travel Expenses (Japan)

Review by DoE

MEXT for Project Expenses (Japan)

FTPC (Fusion Technology Planning Committee)
FPPC (Fusion Physics Planning Committee)
JIFT (Joint Institute for Fusion Theory)
TITAN project (Steering Committee)
Doublet III (Steering Committee)
HFIR (Steering Committee)

Host Institution : NIFS and JAEA (Japan)

Annual Reporting Meeting to Society (Japan)

1

The importance of the Fusion Archives Activity should also be acknowledged. A workshop on thefusion archives was held for the first time in 2005 at UCLA. The resulting fusion historical records
are being accumulated at the Fusion Science Archives at the National Institute for Fusion Science(NIFS).
A previous report, entitled Joint Report: 1980-2000 on the Japan/US Joint Activity*, was publishedby the CCFE in June 2000 on the occasion of the 20th anniversary. Following this same procedure,
we decided to publish a Joint Report mainly for the period of the last ten years, in order to provide
an accounting about this long-standing project and to celebrate the 30th anniversary of the Japan/US
Joint Activity. In the present report, we have tried to include details in the description of theachievements—specifically, highlights of research results and a list of published papers related to theJapan/US Joint Activity for the period of the last ten years. Some of the activities that have been
carried out in 2010 are also included in the present report; other activities are still ongoing and will
be published at the next opportunity.
Overall, the Japan/US Joint Activity in fusion research has been highly productive in terms ofcollaborative projects initiated, papers published, presentations given at workshops and international
conferences, and so forth. Also, the scientific friendships and spirit of collegiality engendered by thevarious types of joint activities have significantly contributed to enhance the research environment inboth countries.

*The 20th Anniversary report is available at the following URL sites:[1] http://www.science.doe.gov/ofes/internationalactivities.shtml on the DOE OFES web page.
[2] http://www.naka.jaea.go.jp/kankoubutu/PDF/JapanUs1980-2000.pdf on the JAEA web page.
[3] http://www.nifs.ac.jp/collaboration/Japan-US/JapanUS-Report.pdf on the NIFS web page.
[4] http://peaches.ph.utexas.edu/ifs/jift/anniversary.html on the JIFT web page.

2

2

CHAPTER 2

Fusion Technology Planning Committee(FTPC)

2.1 Objectives
The FTPC (Fusion Technology Planning Committee) is responsible for organizing US-Japan
collaboration on the research of fusion technology aiming at realization of fusion energy.
After the separation of the FTPC and FPPC (Fusion Physics Planning Committee) in 1991, thesubsections in FTPC are 1) Superconducting Magnets, 2) Structural Materials, 3) Plasma
Heating Related Technologies, 4) Blankets, 5) In-Vessel/High Heat Flux Materials andComponents, 6) Others. Because the joint projects JUPITER-II from 2001 and the TITAN
from 2007 have been intensively executed, the main activities related to 2) Structural Materials
and 4) Blankets have been performed effectively in those projects. The 6) others covers
important subjects such as reactor designs of magnetic or inertia fusion energy (MFE, IFE),
tritium system, fueling system and so on.

2.2 Activities
The collaborations are carried out by workshops and exchange visits of researchers, by
keeping in mind that the number of the collaboration places should be balanced in US andJapan as much as possible. There were also collaboration activities using tele-video system ande-mail, although the number is quite small. During the years of 2000-2009 under US-Japan
collaboration, 74 workshops and exchanges of visits were conducted and 202 researchers weresent to US on various themes related to FTPC. In Japan, 70 workshops and exchange of visitswere held and 181 researchers visited to Japan.

2.3 Administration
As for US-Japan universities collaboration, 5 key-persons from Japanese universities andNational Institute for Fusion Science (NIFS) are designated for the promotion of collaborationin each subsection of FPPC. The present steering committee of FTPC consists of US DoE
key-persons of FTPC and a person in charge from JAEA and a person in charge from NIFS.
The steering committee of FTPC is also attended by the key persons of the joint project and the
few relevant observers from universities and institutes both in US and Japan, according to thenecessity. The steering committee meeting of FTPC is usually held by a tele-video system withcomplementary e-mails once a year.

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2.4 Accomplishments and Highlights
2.4.1 Superconducting Magnets
High-current superconducting magnets with cryogenics systems are key components to be used inmagnetic fusion energy reactors. During the last decade, the US-Japan collaborations focused
mainly on high-temperature superconductors (HTS), because of their large potential to realize highmagnetic field with excellent operational stability.
In fact, the Mini-RT project at the University of Tokyo and the Levitated Dipole Experiment(LDX) project at Massachusetts Institute of Technology (MIT) chose HTS wires to be partiallyapplied in their magnet systems as the world's first applications of HTS for fusion research.
Therefore, the first US-Japan workshop on these HTS systems was held at the University of Tokyoin 2002 to discuss the wire production technology for the first generation HTS (Bi-2223). A second
workshop was held at MIT in 2004 for the first plasma with the levitated coils in Mini-RT and
LDX, and a third workshop was held at NIFS in 2005 to discuss future plans.
Recently, in 2008 and 2009, intensive discussions have been continued by personal exchanges
between NIFS and MIT concerning proposals for joint experiments on Yttrium-based conductor(the second generation HTS) to develop large-current-capacity HTS conductors for fusion magnets.

The technical tour of LDX during the US-Japan workshop on “Use ofHigh-Temperature Superconductors in Fusion ITER Coil Test Results”
at the Plasma Science and Fusion Center, Massachusetts Institute ofTechnology, in October 2004

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2.4.2

Structural Materials

Most of the activities on structural materials for blankets and in-vessel components in fusionenergy reactors have been effectively performed through the joint projects JUPITER-II from 2001
to 2006 and TITAN from 2007. These projects focused on key subjects such as neutron irradiation
effects, thermofluid engineering, tritium behavior, and modeling.
On the other hand the high-power microwave technology developed in fusion plasma heating has
been applied to innovative processing of metallic powder as microwave sintering technology. This
work has been carried out at Pennsylvania State University and NIFS. Powder metallurgy by meansof microwaves is able to achieve no segregation due to grain growth, no re-crystallization, and no
impurity concentration as the powder proceeds below the melting temperature.
Therefore, mutual collaborations by personal exchanges have been intensively performed from2003, for the purpose of developing high-performance low-activation alloys of vanadium andferritic steel, which are the main candidates for structural materials in fusion energy reactors. The
collaborations were productive in revealing the basic physics on thermally non-equilibrium
reactions under microwave irradiations. New ideas to reduce the emissions of carbon dioxide havebeen proposed with the use of this microwave sintering technology.

2.4.3 Plasma Heating Related Technologies
US-Japan collaborations for Radio Frequency Heating Technology have been ongoing since 2000.
Major research institutions in the United States and Japan have taken turns to host workshops forthe exchange of research information and discussion of collaboration activities. At first, meetings
similar to the EU-Japan and US-EU workshops used to be held separately. To improve theefficiency, in 2007 we established a single Japan-US-EU workshop, which has been hosted byrotation since then. The meetings of this combined workshop have been used to discuss major
items required for ITER and future large plasma devices and to initiate and organize a number of
new international collaboration programs.

Workshop on RF heating technology in Nara, 2006

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In the personal exchange collaboration program, the ICRF Groups of NIFS and University ofTokyo have had active collaborations mainly with General Atomics on comb-line antennas, while
the NIFS and JAEA ECH Groups have collaborated with General Atomics and also MIT.
Improvement of the transmission efficiency of high-power millimeter waves was one of the urgent
issues. The output beam radiated from the gyrotron should be led to the corrugated-waveguidetransmission line with an optimized coupling mirror system to take the high transmission efficiency.
The collaboration work evaluated the evolution of the intensity profile along the propagation andconfirmed that the performance of the mirror system design is correct.

2.4.4 Blankets
Most of the activities with regard to blankets have been effectively performed in the joint projects
JUPITER-II from 2001 and the TITAN from 2007. The JUPITER-II project (2001-2006) mainly
focused on the Flibe liquid blanket system, with the flow field and its heat transfer performance
under strong magnetic field being evaluated in order to establish the turbulent heat transfer
modeling of high-temperature and high-Pr number molten salt Flibe flow under strong magnetic
field. In the TITAN project, the thermofluid mechanism of liquid metal and its control techniqueunder strong magnetic field have been mainly evaluated since 2007. Both projects have actively
promoted the training of many young researchers in both the U.S. and Japan, which has strongly
enriched the fusion community as well as contributed to the specific design of the blanket.
In addition to the above-mentioned two projects, HPD (high-power-density) workshops have been
held since 1997 in order to discuss high-power-density devices and thermofluid design. The
activity in this workshop has focused on the engineering issues that are important to achieve ahigh-efficiency energy conversion system. The main issues are to identify and solve theengineering issues in some concepts of the first wall cooling system and the blanket system, andthen to propose a road map for future development. Information exchange about concepts for aliquid blanket system has continued at the workshops, and personal exchanges have been also
performed to solve each of the important issues. Specific subjects discussed are (1) Development ofhigh-heat-flux components satisfying heat removal performance, integrity and maintenanceflexibility, (2) Free surface flow including turbulent heat transfer from the liquid surface and its
enhancement under a magnetic field, (3) Liquid lithium blanket system that uses coating material
for corrosion resistance and its structure optimization, and (4) Diagnostic techniques for highPr-number and complex flow field in a heat transfer promoter pipe under magnetic field. Also, at
the kickoff stage, gas cooling and gas-solid suspension cooling systems were discussed including
heat-exchange systems. In order to propose a road map for innovative blanket design, thePlasma-Wall Interaction group, which has been enhancing the specific blanket design, hasparticipated in the above-mentioned HPD workshop.

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A group photo during the U.S.-Japan Workshop on “Fusion High PowerDensity Components and System and Heat Removal and Plasma-Materials Interactions for Fusion” at Santa Fe in November 2006.

2.4.5 In-Vessel/High-Heat-Flux Materials and Components
In this category, mainly four activities have been intensively performed during the past ten years,
namely, 1) Divertor plasma experiments, 2) Collected dust analyses, 3) Wall conditioning analyses,
and 4) Workshops on these research areas. Divertor plasma experiments have been carried out by
personal exchanges with the use of the NAGDIS-II facility at Nagoya University and the PISCES
facility at UCSD. Well-controlled linear plasma experiments in NAGDIS-II led to significant
progress in understanding the physics of plasma detachment. Engineering research has been
intensively performed to explore specific properties of plasma-facing materials, such as tungsten,with the use of high particle fluxes in PICSES. The first analysis of collected dust in Japan was
performed with LHD in March 2001 in a collaboration with Idaho National Laboratory (INL). The
results were compared with those from tokamak machines in EU and US. These experimental
techniques established in LHD were subsequently applied in JT-60U. Wall conditioning of theplasma-facing surfaces of in-vessel components is essential for well-controlled surfaces to achieve
high plasma performance with good reproducibility. Experiments using DiMOS in DIII-D werecarried out to characterize boronized wall samples.
The workshop on "High Heat Flux Components and Plasma Surface Interactions for Next Fusion
Devices" has been held almost every year, alternately in US and Japan. Already from the early daysof the US-Japan program, this workshop has covered a broad range of subjects on Plasma Wall
Interactions (PWI). During the past decade, the workshop has focused mainly on Plasma Materials
Interactions (PMI) in order to understand microscopic mechanisms under multi-particle irradiationand to extrapolate the behavior of materials to burning plasma devices by means of modeling andnumerical simulations.

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2.4.6 Others
One of the other main activities related to fusion technology is reactor design. A US-Japan
Workshop on Fusion Power Plants and Related Advanced Technologies has been held almost every
year for more than a decade. In recent years, EU and other countries, including China, have also
participated in this workshop, which has featured discussions on wide-ranging topics related tosystem optimization of a DEMO and a commercial reactor. Two personal exchange programs werealso carried out. These programs contributed to the progress in design studies in both the US andJapan through mutual evaluation and comparison of design concepts.
A workshop on fabrication, injection, and tracking of IFE targets has also been held. Detailed
technical information specific to each researcher’s work was exchanged and has led to thewidening of the collaborations in this research field.

A group photo during the U.S.-Japan Workshop on Power Plant Studies andRelated Advanced Technologies with EU Participation at UCSD in Feb., 2006.

Another important collaboration between Japan and the US is concerned with tritium handling andcontrol technology. Analytical methods developed in basic investigations at Japanese universities
were applied to analyze experimental data from US facilities. Since Japan has no place to gain
experience in handling large amounts of tritium, the information obtained through this program wasquite valuable for the Japanese participants. Important information on education and training of
new up-and-coming tritium researchers has also been transferred through this program.

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2.5 Highlights
Application of High-Temperature Superconductors in Fusion Research
Category : Fusion Technology
Year-Number :the “ITER Coil Test Results”. By this time, both the LDX
and Mini-RT devices were completed and results on thecommissioning tests of their magnet systems and firstplasma experiments were reported. The first plasma of
Mini-RT was successfully obtained in February 2003, andby April 2004, the floating coil was levitated over an hourwith a high positional accuracy of ±20 Pm. In LDX,
although levitation was not possible (at that time) due to atrouble in the HTS levitation coil, the first plasma wasproduced in April, 2004. In Figs. 1 and 2, the floating coils
and first plasmas obtained by LDX and Mini-RT are shown.

2001-FT1-2, 2004-FT1-2, 2005-FT1-1, 2009-FT1-1

Name: Toshiyuki Mito, Nagato Yanagi,
Yuichi Ogawa, Joseph V. Minervini
Affiliation (T.M and N.Y): National Institute for
Fusion Science, (Y.O): The University of Tokyo,(J.V.M): Massachusetts Institute of Technology
Application of high-temperature superconductors (HTS)
in fusion research is regarded as a pioneering work, and the
US-Japan collaboration on this topic was started about ten
years ago when the application of HTS was an emerging
technology to be considered in real use. Despite thissituation, both the Mini-RT project at the University ofTokyo and the Levitated Dipole Experiment (LDX) projectat Massachusetts Institute of Technology (MIT) chose HTS
wires to be applied partly in their magnet systems as theworld’s first applications of HTS for fusion research.
At that time, the wire production technology for the first
generation HTS (Bi-2223) was being established andinstitutions, universities and industries in the US and Japan
were fiercely competing to manufacture longer and superior
wires. Real applications were beginning to be considered
for industrial and electric devices, such as cables, motors,
transformers and magnets of pulling systems for silicon
single crystals. However, it was too early to consider
applying HTS for plasma confinement devices in fusion
research, other than in current-leads. In these circumstances,it was a great opportunity to start this challenging
collaboration as a US-Japan joint program.
The first activity of the collaboration was a workshop
held at the University of Tokyo from February 4 to 6, 2002,
titled “Application of High Temperature Superconducting
Coils for Fusion Plasma Experimental Devices”. In thisworkshop, fruitful discussions were made on a wide rangeof physics and technological issues, such as evaluations on
the electromagnetic properties of HTS wires and on
manufacturing methods of Yttrium-based coated-conductor
wires (the second generation HTS). The discussion was
focused on the two projects of plasma confinement devices
both using levitated superconducting coils. In the US, LDX
was being constructed as a joint research of MIT and
Colombia University, whereas in Japan, the Mini-RT
project started as a joint research program of The
University of Tokyo, National Institute for Fusion Science(NIFS) and Kyushu University. In LDX, the floating coil
was wound using Nb3Sn superconducting wires, whereas
the levitation coil used Bi-2223 HTS wires. In Mini-RT,
the floating coil was wound with 400 m of Bi-2223 wires.
Fruitful discussions were carried out especially on the R&D
activities for their superconducting magnet systems and thefuture prospects of their research.
The second workshop was held at MIT from October 12
to 13, 2004 with a title “Use of High-Temperature
Superconductors in Fusion” under the joint workshop for

Fig.1: The floating coil and the first plasma of LDX.

Fig.2: The floating coil and the first plasma of Mini-RT.
The third workshop was held at NIFS on December 9,2005 with a title “Application of High-Temperature
Superconducting Coils in Fusion Plasma Experimental
Devices”. Based on the successful results of both LDX andMini-RT, long-term programs on applying HTS for fusion
research were discussed. The development of HTS wires tobe applied in large-current capacity conductors for fusion
magnets was the common interest from both the US andJapanese sides. In December 2008 and October 2009,
meetings were held at NIFS and MIT, respectively, todiscuss the possible program for developing large-current
capacity HTS conductors for fusion magnets by focusing on
the Yttrium-based coated-conductors. The plausible futurecollaboration was also discussed, including joint
experiments of reduced-scale conductors using thesuperconductor testing facility at NIFS.

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Microwave Processing of Metallic Powders for Fusion Applications
phase transitions. For example, the nano-crystallographic of ferromagnetic powders in which the hard magnetism
converted to very soft one. These experiments show that the
microwave couples with different energy path on the phasetransitions.
These phenomena require very sophisticatedstudies of renormalization theories, molecular dynamics,
etc. on the bases of ab initio calculation performed by M.
Tanaka.
The theoretical researchs are going to answers;“ how to excite the collective motion in solid material bysuch monochromatic electromagnetic wave? “ and “ Whatis the mechanism to mitigate a driving microwave to a wide
frequency spectrum of the blackbody radiation? ”. This
innovative research is going to open a new door to makebulky nano materials of glassy structures with nanomagnetic domains form the micron order crystals.
(2) Contribution to building a low carbon society
The joint discussion with Penn state-U and NIFS,
the idea emerged for the steel making process on largescale comprehensive energy saving. If the electric power togenerate the microwave would be supplied by renewablesources or the fusion in the future, the emissions of carbon
dioxide that caused by burning coke on making pig iron
reduced to the 40% in comparison to the existing blast
furnaces. The impurity contents are less than 1/10~1/50 incomparison to cast irons produce by existing blast furnace.
It suggests new technology to serve ultra high purity steels
for fusion reactor.
The amount of microwave power is estimatedexperimentally to 500kWh / t. Scales of these microwave
source are equivalent to the gyratrons or klystrons used forsuch large-scale nuclear fusion research such as ITER and
LHD, JT60. This is an example to be expected leading the
big social return of high technology developed on fusion
studies.

Category: Fusion Technology
Year-Number: 2003-FT2-1, 2-3, 2004-FT2-1, 2-3,
2005-FT2-1, 2-3,2006-FT2-1, 2-2,2007-FT2-1, 2-2
Name: Motoyasu Sato* M. Tanaka*,
Dinesh Agrawal**, Rustum Roy**
Affiliation:National Institute for Fusion Science*
Material Research Laboratory, Pennsylvania State
University**
The Pennsylvania state university, in 2000,
demonstrated the world's first microwave sintering of
powder metallurgy to the iron-based metal, NIFS
developed microwave sintering technologies by applying
the high-power microwave experiences  on fusion
experiments to the dielectric ceramics. The cutting edgelaboratories promoted researches on the framework of thejoint Japan-US collaboration to both the basic research andapplications of microwave sintering technologies. The
vanadium steel alloy and ferrite steel are expected to fusion
reactor materials. The powder metallurgy by microwave
could produce no segregation due to grain growth, no recrystallization and no impurity concentration as it proceeds
below the melting temperature.
(1) Results on Basic Physical Properties
The first year, the "In-Situ observation
experiments on sintering process " proposed by Japan.
NIFS took the newly developed digital microscope to the
U.S.A.. Prof. R. Roy of Pennsylvania state university
predicted the thermally non-equilibrium reactions under
microwave irradiations. The observations reveled that the
localized hot spots were created and maintained for asignificant period of time. The hot spot diminishes in a few
seconds and loses its energy quickly to the surrounding
environment. They reconstructed the micron order crystals
into the continuous nano-magnetic domains Suchmicroscopic rapid cooling causes the development of nanodomains. New hot spot continue to get generated in otherregions of the sample. This chain process eventually causes
the nano-domains spreading all over the material.
Recently, the striking similarity of ultrasound andmicrowave processing at high temperature was pointed out.
It remained us the word of “coherency”. The series ofexperiments suggested that the irradiation of magnetic fieldwith high monochromatic frequency spectrum excites
oscillations of electrons in the ferromagnetic material
coherently directly. The Gibbs free energy (G = H – TS)
contains two different ordering terms of the disorderedthermal motions (origin of high entropy), the coherent
kinetic motions and microscopic ordered structure (originof low entropy). As the microwave processing uses
monochromatic frequency, the electric or magnetic fields
generate ordered motions in the material on the first step.
The entropy of coherent phonons is lower than the random
motion of thermal photons. The decreasing of activationenergy has been observed in the reduction process oftitanium oxide (TiO2) under the irradiation of microwave
magnetic field. The fall of energy can also be seen on the
















Hot Spot

Fig. 1 In-situ observation of hot spot in a ferrite sample exposed toH- field in 2.45 GHz 5 seconds after microwave turned on, thebrightest spot exceed 1200 degree C, the dark part was less than
800 degree C. The scale is 100 micron. Temperature gradient wasestimated to a few thousands degree C / 1 mm.10RF Heating TechnologyCategory:Fusion Technology/ Steady-State Operation
Year-Number:2000-FT3-8, 2000-FT3-7, 2001-FT3-01,

were reported. Impressive new gyrotron results were alsopresented: 1.3 MW/1.5s at 110GHz from JAERI and
0.9MW/55s at 140 GHz from EU.
In 2003, the workshop was held at JAEA (former
JAERI). Observers from KAERI(Korea) joined the meetingin addition to US, EU and Japan, which further
internationalized the workshop. Successful results werereported on the evaluation study of the ECH transmission
system between NIFS and MIT and the high power test of
the remote steering antenna by JAERI and GA, which were
proposed in the previous meeting.
In 2005, the workshop was held in Santa Cruz, USA.
Several significant gyrotron advances were reported. The
testing of a 1.5 MW CPI tube began at GA. GA also began
to replace Gycom tubes with CPI tubes. Successful
development of gyrotrons for W7-X (1 MW/140GHz) andITER (2MW/170G) were reported by Karlsruhe.
In 2006, the workshop was held in Nara, Japan. The
ITER construction began to take shape on a large-scale. A
JAEA gyrotron demonstrated 0.82MW/10min. As for ICRF
heating, LHD 54 min/1.6 GJ steady state operation wasreported, which showed RF heating was suitable for steadystate operation.
In 2008, the matter of concern was how the workshop
members could cooperate for the resolution of the issues
which emerged as the ITER development progressed. In thefield of ECH, the quality of diamond windows became anissue. It was also when W7-X mass-produced gyrotron
quality became an issue. GA and some other institutes
reported mechanisms for arcing in vacuum relevant to
ICRH antennas.
In 2009, JAEA mostly fulfilled the ITER specificationof 1 MW/30 min for gyrotron development and iscontinuing to make further improvements. Development of
a 2MW co-axial gyrotron by the EU has progressed and its
completion is expected.
Since 2008, a collaboration has been ongoing between
GA and JAEA on high power, very long pulse testing of
ITER related ECH components using the 170 GHz JAEA
test stand. So far, various miter bends, switches, and a DC
break have been tested. The overall loss in the test
transmission line has also been examined by thermal
imaging with these components.
A collaboration has continued since 2006 on combline
antenna for use in the TST-2M tokamak at the University ofTokyo. A fast wave combline antenna originally made by
GA for the JFT2M tokamak collaboration was moved to
TST-2M along with the 200 MHz transmitter. During the2006 visit, electrical characteristics of the antenna were
measured. A clear pass-band was observed in the frequency
range of 160-220 MHz, which includes the planned
operating frequency of 200 MHz, and the excitation of a
travelling wave with a parallel wave-number of 22 m-1 was
confirmed and it is now installed and being run at highpower. A variation of the combline antenna to launch
lower hybrid waves at the same frequency for current rampup is now being designed by GA.

2002-FT3-5, 2003-FT3-3, 2003-FT3-2, 2005-FT3-4, 2006FT3-1, 2006-FT3-2, 2008-FT3-2, 2008-FT3-4, 2009-FT3-2

Name: T.Mutoh, K. Ohkubo, T.Seki, Y.Takase1), C.
Moeller 2)
Affiliation: National Institute for Fusion Science,
1)
University of Tokyo, 2) General Atomic

The US-Japan collaboration for Radio Frequency
Heating Technology has been ongoing since 2000. Major
institutes in the United States and Japan have hosted
workshops in turn to exchange research information anddiscuss collaboration activities. Originally, the EU-Japanand US-EU workshops were held separately. To improve
efficiency, we established a single Japan-US-EU workshop
in 2007 which has been hosted by rotation since then. The
exchange of researchers was made in parallel with theworkshops.
In the personal exchange collaboration program, the
NIFS ICRF Group has mainly collaborated with General
Atomics for the combline antenna actively while the NIFS
and JAEA ECH Groups have collaborated with General
Atomics and MIT. The followings are the highlights of theworkshops in each fiscal year and the personal exchange
activities.
In 2000, diamond windows started to become practicalfor ECH vacuum windows following the workshop in
Princeton. Practical use of diamond windows accelerated
rapidly after the exchange of information about the coolingstructure at the vacuum seal. The remote steering antenna
was devised at GA and the application to ITER was
proposed. The ECH and ECCD experiments at JT-60 andthe success of electron heating to a Te of 15keV and ECCD
of 0.2MA were reported. At the time, low transmission
efficiency of the transfer lines was a problem.
At that same time, collaboration research aimed atincreasing the standoff voltage of ICRF antennas forheating experiments began between ORNL and ASDEX.
As for LHD, one minute of steady state plasma sustained by
ICRF was reported.
The US-Japan RF technology workshop in 2001 wasjointly hosted with “EU-Japan workshop on antenna
technology” in Inuyama. Researchers from US and EU
gathered in Inuyama to discuss RF technology widely in themeeting. Low power experimental results on the remotesteering antenna were report by both US and the EU, which
confirmed the efficacy of the antenna. ECH experiments
were actively conducted with JT-60U, LHD, CHS,
Heliotron-J and DIII-D. As a result, achievement of highelectron temperature, stabilization of NTM instability, ITB
formation and effective plasma production were reported.
In 2002 the workshop was held in Los Angeles.
Starting with this meeting, US-Japan workshop joined with
EU-US and EU-Japan RF technology workshops toimprove the efficiency. Regarding ECH, development of
the remote steering antennas improved experimentally aswell as in analysis. Methods to expand the steering range

211-9

Beam Coupling / Mode Content Analysis in Transmission Line of Electron Cyclotron Heating System

Category : Fusion Technology
Year-Number :In the LHD-ECH system, the propagation direction,mode content and the field structure were analyzed in the
mirror system and waveguide transmission line (Table I),
improving the transmission efficiency as the original task6.
The experimental verification of the phase retrieval, newdefinition of the irradiant waveguide modes and their use
for the mode expansion deserved a special mention incontribution to the radio frequency and mm wave
technologies.

2000-FT3-3, 2003-FT3-7, 2007-FT3-6, 2008-FT3-1

Name: Hiroshi Idei, Takashi Shimozuma,
Michael A. Shapro, Richard J. TemkinAffiliation (H.I): National Institute for Fusion Science(2000), Kyushu University (2003/2007/2008), (T.S):
National Institute for Fusion Science, (M.A.S and
R.J.T) Massachusetts Institute of Technology (MIT)475mm

Improvement of the transmission efficiency of highpower millimeter waves was one of the urgent issues on theElectron Cyclotron Heating (ECH) system in the Large
Helical Device (LHD). The output beam radiated from the
gyrotron should be led to the corrugated-waveguidetransmission line with the optimized coupling mirror
system to take the high transmission efficiency. We havebeen collaborating with MIT group in USA on the couplingof the gyrotron beam into the transmission line1. The
evolution of the intensity profile along the propagation was
evaluated from the IR images at the target in the highpower test. The phase profiles required in the mirror systemdesign were retrieved from the intensity evolution along the
propagation. The performance of the designed mirror
system was confirmed to work correctly at the low power
test facilities2. (2000)
The alignment of the beam position and angle (within +/1mm and +/- 0.2 degrees) are important to attain the hightransmission efficiency. The principle experiments shownin Fig.1 were conducted to study of the phase retrieval
process and the mechanisms of the unwanted mode
excitation. The phase profiles retrieved from the intensity
evolution in the experiment were compared to those
directly measured at the low power level in detail, and thephase retrieval process was verified experimentally3. The
phase profiles retrieved at the propagation position ofz=150mm coincided well with the measured profiles, as
shown in Fig.2. The beam position, radius, symmetry,kurtosis were evaluated with the moment theory including
higher orders, describing the beam property. (2003)
Furthermore, a new alignment method of thetransmission line basing on the phase retrieval (Fig. 1)4 was
proposed. The irradiant waveguide modes were defined ina free-space propagation to analyze the mode content in the
waveguide transmission5. In the definition of the irradiantwaveguide modes, the fields radiated from the waveguideaperture in Fig.1 were used. The mode content in the
waveguide transmission was evaluated from the field
intensity and phase profiles measured at a certain
propagation position. (2007)
The direct phase measurements were not available forthe high power test and the alignment of the LHD-ECH
transmission line. The new mode retrieval method was
proposed for the high power application. In this approach,the phase retrieval process was not required. This new
approach was confirmed to be effective to analyze themode content transmitted in the waveguide line. (2008).

xywaveguide axis

x0
x0 x 0z

1 degreez = 150mm ....... .
a 88.9mm diameter 㻌corrugatedwaveguide of 1m longFig.1: Experimental setup the principle experiments forbeam coupling and mode content analysis

cut at <y>=const.
Retrieval from data at z=15/25/35cm
Retrieval from data at z=20/30/40cm
Measurement data at z=15cm


Beam Center







Phase [ radian ]Phase [ radian ]









cut at <x>=const.
Retrieval from data at z=15/25/35cm
Retrieval from data at z=20/30/40cm
Measurement data at z=15cm


Beam Center

x [mm]
















y [mm]

Fig.2 : Comparison between the retrieved and measured
phase profiles
Table I :Result of modecontent analysis. Main
HE11 mode of 89% istransmitted. The others
are unwanted modes.

Fig.3 : a) Measured
amplitude profile and b)
retrieved phase profile
1) M. A. Shapiro, et al., Fusion Eng. and Design, 53 (2001) 537
2) T. Notake, H. Idei, et al., Fusion Eng. and Design, 73 (2005) 9
3) H. Idei, et al., IEEE Trans. on MTT, 54 (2006) 3899
4) T. Shimozuma, H. Idei, et al., JPFR, 81 (2005) 191
5) H. Idei, T. Shimozima, et al., Proc. of IRMMW-THz 2007, 69
6) T. Shimozuma, H. Idei, et al., PRR, 5 (2010) S1029

12

Measurement
ofof
RF
RelevantECH&CD
ECH&CDTransmission
TransmissionLine
Measurement
RFTransmission
TransmissionMode
Mode inin ITERITER RelevantLine
Category : Fusion Technology
Year-Number : 2007-FT3-3, 2008-FT3-5, 2009-FT33
Name: Yasuhisa Oda1, Ken Kajiwara1, Koji
Takahashi1, Atsushi Kasugai1, Michael
Shapiro2, Richard J. Temkin2, Keishi
Sakamoto1
Affiliation: 1Plasma Heating Research Group, Naka
Fusion Research Institute, Japan Atomic Energy
Agency, 801-1 Mukoyama, Naka, Japan
2
Plasma Science and Fusion Center, Massachusetts
Institute of Technology, 167 Albany St., Cambridge,
MA, USAtransmitted through the TL without significant mode
conversion loss.
When two or more modes travel together down the
waveguide, the center of the microwave beam will, in
general, be offset from the axis. Also, when the modes
reach the end of the waveguide, they will radiate into spacewith a tilt angle. The offset and tilt angle may be a problem
in the launcher / antenna system for plasma heating andcurrent drive. The case of two modes traveling in the
waveguide has been analyzed in a recent paper by Kowalski
et al. [2]. The paper shows that the offset varies with
distance along the waveguide as a cosine wave, while thetilt angle varies as a sine - that is, the tilt angle is ninety
degrees out of phase with the offset. With proper
normalization, the square of the offset and the square of thetilt angle can be added to express a conservation theorem[2]. The variation of offset and tilt angle repeats with
distance down the waveguide at the beat wavelength of thetwo modes. For the present case, we have most of thepower in two modes - the HE11 mode and the LP11 mode but there is still significant power in a series of higher
modes. For the present case, the experimental values of thetilt angle and offset are plotted vs. extended waveguidelength in Figs. 2 and 3 respectively. We also show fits tothe tilt angle and offset using sine/cosine functions with aperiodicity of 5 meters, which is the beat wavelength of thetwo major modes (LP01 and LP11). The measured values oftilt and offset agree well with the theoretical sine/cosine
curve fits. We see from these results that as the microwaves
propagate down the waveguide, they will always have someamount of either tilt or offset or both.

The 170 GHz transmission line (TL) for the electron
cyclotron heating and current drive (EC H&CD) system in
ITER requires more than 90% power transmission
efficiency from the gyrotrons to the plasma using about 100
m length corrugated waveguides. For high transmission
efficiency, the good purity of HE11 mode is necessary(95%). In this study, the transmission mode in the 170 GHz
high power long transmission test line for ITER, which
consists of the 63.5 mm corrugated waveguides, wasmeasured and the effect of higher order modes (HOMs) in
ITER’s transmission line is discussed.
The millimeter wave beam was generated by the 170
GHz high power gyrotron [1] and coupled into thecorrugated waveguide through the Matching Optics Unit
(MOU) constructed with two phase correcting mirrors. The
power is transmitted to the dummy load. Two high powertransmission test lines were prepared. One is a short range
TL (7 m) and the other is a long range TL (40 m) as shownin Fig. 1. The direction of the RF power is selected by the
waveguide switch. The TL system has 7 miter bends
including the waveguide switch in the long range TL.

Fig.2. Dependence of tilt
Fig.3. Dependence of offset ofangle of radiated beam on
beam center at waveguide outlet
length of extended
on length of extended
waveguide.
waveguide.
Thus the LP11 mode generated at the TL input couldmode
at theTLinput
inputfor
could
Thus
LPat
affectthe thebeam
TLgenerated
output which
is an
the
11 theaffect the beamat the coupling
TL outputefficiency
which is an
inputMOU
for thelauncher.
The initialat theislauncher. The
initial the
coupling
efficiency
at the MOU
isimportantto improveradiation
characteristics
from theimportant to improve the radiation characteristics from thelaunchers.
launchers.
The research at MIT was supported by the US DOE
Theandresearch
MITProject
was supported
OFES
the US at
ITER
Office. by the US DOE
OFES and the US ITER Project Office.
[1] K. Sakamoto et al., Nature Phys. 3, 6 (2007), p. 411.
[1] E.
K. J.
Sakamoto
Phys.Conf.
3, 6 (2007),
411.
[2]
Kowalskietetal.,al.,Nature
Proc. Intl.
IR, MMp.andTHz[2] E.Waves,
J. Kowalskial., Proc.
Intl.R2D01,
Conf. IR,
MM
and Proc.,
THz
Busan,etKorea,
Paper
IEEE
Conf.
Waves,
Busan, Korea, Paper R2D01, IEEE Conf. Proc.,
Sept.
2009.
Sept. 2009.

Fig. 1. Schematics of JAEA transmission test line. The
diameter of the waveguide was 63.5 mm.
Using measured IR patterns, the mode content was
retrieved using the MIT codes. A set of linearly polarized(LP) modes is used. In this analysis, the four LP modes are:fundamental mode LP01 (HE11), LP11 (even and odd), andLP02 (HE12) modes. There was a small difference in themode content between long TL and short TL. This indicatesthat the mixture of HE11 and LP11 modes could be

2 13
- 11

Fusion High Power Density Devices and Thermofluid Design
Category: Fusion Reactor Technology/ Diverter,
BlanketYear-Number : 2000-FT4-1,2,6,7,8 2001-FT4-01,02,07

2) As for liquid lithium blanket system, corrosion resistanceof coating materials was discussed and the optimization of
structure has been performed to show a development plan
based on existing materials and fabrication techniques.
This activity is extended to development of new flow
channel composing of three insulated surfaces by threelayer wall. For this option , basic experimental research is
being conducted to demonstrate the performance2).
3) The probes suitable for visualizing the flow structure
were evaluated for a heat transfer promoter pipe that would
be required for hi-Pr number fluid Flibe. A backward
scattering type of the probe was selected in consideration of
the complicated flow structure around the promoter surface.
In addition, the test section to reduce the effect of the laser
refraction is designed including the utilization of thematched refractive index method.
Finally, theintroduction of the test section to the Flibe simulated flow
loop was discussed in detail as well as the design of an
entrance distance to the test section, and measuringconditions. Based on the experience, experimental datafor heat transfer in a pipe filled with pebble bed arecollected 3).
4) The Flibe blanket system proposed by the Japanese side
is initially focusing on demo reactor because the operating
temperature of Flibe is too high to be applicable to ITER
TBM due to the limitation of maximum allowabletemperature for available structural materials. Throughdiscussions, this problem was solved by changing thecomposition ratio of LiF and BeF 2 to reduce the melting
temperature, which led to a design window of Flibe TBM
and shows a road map to a blanket system of demo reactors
by changing the BeF 2 ratio, allowing higher heat transfer
performance, with the development of structural materials4).
In the development of liquid blanket system, it
becomes possible to describe the road map for innovative
system through the understanding of present technologies
and provide a clear direction for future development andcollaboration.
1) S. Satake et al., Fusion Engineering and Design, 61-62,(2002), 95.
2) M. Aoyagi et al., ISFNT 9, (2009), China (to be
published)..
 N. Seto al., Fusion Engineering and Design, 83, (2008),
1102.
4)H. Hashizume et al, Fusion Science and Technology, 56,(2009), 892.

2002-FT4-5, 2003-FT6-1, 2004-FT5-4, 2005-FT5-2,
2006-FT5-2, 2008-FT5-1

Name: Sabro Toda, Hidetoshi Hashizume, *Shinichi
Satake, Kazuhisa Yuki**Clemet Wong, ***Neil Morley

Affiliation:Tohoku University, *Toyama University,**General Atomics, ***UCLAIn order to realize fusion reactor in the near future,
the activity in these projects is focusing on one of the mostimportant engineering issues, how to achieve high thermal
efficiency in the energy conversion system. The main
issue in these activities was initially thermofluid dynamics
in high heat flux components like divertor and finallydesign on blanket system not only for ITER but also for thedemo reactor. Information exchange in terms of concepts
on liquid blanket system has continued in the workshops
and personal exchange has been performed to solve
important problems. Main subjects discussed are;1) to identify engineering issues in present concepts offirst wall cooling system and blanket system and then to
analyze governing phenomena .
2) to propose solutions for the critical engineering issues
and then show a road map to future development.
Through these activities, following results can besummarized:
1) In the development of high heat flux components, it isinevitable to discuss feasibility satisfying several
requirements like heat removal performance, integrity andmaintenance flexibility. A free surface flow system as achamber protection scheme is one of the attractive
candidates. In case of the cooling of the first wall in anadvanced nuclear fusion reactor, the liquid film surface
becomes high temperature due to high surface heating fromthe plasma, and the control of evaporation from the liquidsurface is needed to minimize contamination to the plasma.
Therefore, in order to reduce the surface temperature, it isimportant to elucidate the mechanism of turbulent heattransfer from the liquid surface and the promotion of heattransfer by using the turbulence mixture and then a DNS ofliquid film cooling in a nuclear fusion reactor was
performed by Japan and UCLA members, and the relation
between a magnetic orientation and turbulent flow statistics
are included in the consideration. The streaky structurewith streamwise applied magnetic field are elongated to thefree-surface region. The phenomena are corresponding to
the reduction of stream wise turbulent fluctuation. From the
DNS modeling, Reynolds averaged model and the SGS
model for free surface with MHD will be developed byusing DNS database in the near future, and the LES will
have the ability of providing simulation for the fusion
facility1).

2 14
- 12




Current plasma wall interaction’s issues in fusion devices(Divertor simulator experiment in NAGDIS-II and surface analysis of dust particles and boron)

Category : Fusion Engineering
Year-Number : 2000-FP5-8, 2000-FT6-7, 2007-FT52, 2009-FP2-2
Name: S. Takamura*, S. Luckhart**,P. Sharpe***,D. Petti***, N. Ashikawa****
Affiliation: *Nagoya Univ., **UCSD, ***INL 㧘****NIFS

and target plates in the vacuum vessel, surface mass densityof dusts is similar to each location [3].
Dr. N. Ashikawa (NIFS) and Dr. C. Wong (GA) havebeen investigated the characterization of boronized wallin DIII-D. Boron films on stainless steel material probes
coated by boronization in DIII-D have been analyzed by Xray photoelectron spectroscopy (XPS) and the chemicalbindings of deposited layer with boron are shown. At the
top surface of boron film, high concentrations of graphite
peak, B-B and B-C bindings are observed and a boronoxide did not have strong intensity. And then, capacity ofoxygen gettering into boron film has still kept after theexperimental campaign in DIII-D. We discussed about
DiMES system (it is the movable material probe system) in
DIII-D during the same program. From under this
discussion, Dr. N. Ashikawa and Dr. D. Rudakov started ajoint experiment of dust dynamics using pre-characterized
dust particles from 2008.

In this section, three kind of topics based on plasma
wall interactions are shown as followings, 1) Divetor
plasma experiment using NAGDIS-II, 2) Colleted dust
analysis in LHD and 3) boronized wall analysis in DIII-D.
Reduction of huge plasma heat load onto the divertor
plate is one of the most critical issues in order to establish
long and/or steady state plasma operation in next
generation fusion devices. From Prof. S. Takamura(Nagoya Univ.), Dr. D. Whyte, and Dr. E. Hollmann
supported by the US-Japan collaboration program, studied
the fundamental physics of plasma detachment, which isthought to be the most promising method to reduce the heatload, and has been intensively investigated by using thedivertor simulator, NAGDIS-II.
Volumetric plasma recombination was found to play
an essential role in detached plasmas, because continuum
and a series of line emissions from highly excited levels
were observed in the detached plasmas.
In order to understand the energy balance between
electrons, ions and neutrals, we conducted the ion
temperature measurement by detecting Doppler broadening
of HeII (468.6nm). Figure 1 shows that Te in thedownstream rapidly decreases with neutral pressure P,
while Ti is gradually decreasing. Around 6 mTorr, Te and Ti
become almost equal, which suggests that the temperaturerelaxation process between electrons and ions contributes
to a decrease in Te. Numerical simulation with 2D fluid
code B2 also revealed that the electron-ion energy
exchange process accompanied with the charge exchange
process between ions and neutrals is responsible for theelectron temperature drop along the magnetic field leading
to Te below 1 eV, where the three body recombination
occurs, leading to the detached plasmas [1-2].
Dr. P. Sharpe, Dr. D. Petti (INL) and Dr. A. Sagara(NIFS) investigated deposited dusts into the plasma
vacuum vessel in LHD. The INL group has collected theamount dust corresponding to the surface areas. . In thisstudy supported by the US-Japan collaboration program,dusts in helical fusion device were investigated as new typeof data. Colleted amount of dusts at a lower region is about
58.7 mg/m2 and it is smaller than results in JET and
ASDEX-U. An averaged diameter of dusts is about 9.64
Pm made by carbon and stainless steel in LHD. From
results of angler dependence between a horizontal plane

Fig. 1 Dependence of (a): electron temperature Te
and ion temperature Ti; (b): electron density ne,measured at upstream and downstream, on theneutral gas pressure P.
1) E. M. Hollmann, D.G. Whyte, D. Nishijima, N. Ohno
et al., Phys. Plasma, 8 (2001) 3314-3320.
2) D. Nishijima, D. G. Whyte, Y. Uesugi, N. Ohno et al.,Proc. of 26th EPS Conf. on Contr. Fusion and Plasma
Physics, Vol. 23J (1999), pp.485-488.
3) J.P. Sharpe, V. Rohde, A. Sagara et al., J. Nucl. Mater.
313-316 (2003) 455-459.

15

High Heat Flux Components and Plasma Surface Interactions for Next Fusion Devices(Heat Removal and Plasma Material Interaction for Fusion)
Category : Fusion Engineering
Year-Number : 2000-FT5-1,2001-FT5-04, 2002-FT51,2003FT5-1,2004-FT5-3,2005-FT5-3,2006-FT53,2007-FT5-1,2009-FT5-1
Name: N. Noda, Y. Ueda, R. Nygren
Affiliation: NIFS, Osaka University, SNL

intrinsic and neutron-induced defects. Therefore, He effects
on T retention need to be investigated. Experiments of
He/D simultaneous implantation into tungsten have been
performed in PISCES at the low temperatures. For pure D
plasma cases, high flux plasma caused blistering on
tungsten3). In this case, D atoms are accumulated not onlyin grain boundaries but also in grains. The mechanism of D
retention in grains could be due to over-saturation of D
atoms and successive void formation.
They also found that He implantation greatly
reduced D retention and blistering, see Fig.24). Thissignificant effect has been observed in several plasma andion beam experiments. Reduction of retention could be due
to formation of connected pores to the surface which
enhance D diffusion and desorption from the surface.
By virtue of these researches, the understanding oftungsten PMI in fusion reactor environments are increasing.
Therefore, this workshop will surely give us further
contributions in fusion development in future.

Plasma facing components of fusion reactors have towithstand high heat and particle fluxes for several years tokeep the compatibility with burning core plasmas.
Development of the plasma facing components andmaterials is a very important and urgent issue for realizationof fusion reactors.㩷
This workshop is dealing with several important andtimely topics in this field. The participants from Japan andUS with some from the other areas exchange theinformation about current status of research anddevelopment of this field and make fruitful discussions.
This workshop greatly contributes to development offusion science and technology not only for Japan and US
but also all over the world.
㩷 㩷 㩷 㩷 㩷 In this report, works on tungsten, the most importantmaterial for plasma facing components and blanket firstwalls, discussed in this workshop are briefly introduced.
Tungsten has several preferable features for the reactor firstwalls such as a high melting point, a high thermal
conductivity and low tritium retention. Several issues,
however, such as mitigation of impacts on core plasma
performance as well as mitigation of material degradationby the plasma flux and the neutron flux must be solved. In
this report, the results on the effects of high flux D and He
plasma irradiation to tungsten are described. With thisenergy, no displacement damage of tungsten lattice takes
place.
By Nagoya university group, Prof. Takamura andProf. Ohno were making researches on He plasma effects
on tungsten for many years. They found that sub-micronscale holes, so called He bubbles, were formed by He
plasma at the temperature above 1600 K. The He ion
impinging energy necessary for He bubble structure wasonly about 6 eV or above, see Fig. 11), which is much below
the threshold of the displacement energy of tungsten atoms.
He bubble formation probably takes place byrecombination of He atoms and thermal vacancies followedby diffusion and agglomeration of these He/vacancy
complexes. In addition, for the temperature above about1100 K, it was found that the cotton-like structure wasformed by tungsten nano-fibers with the diameter of a few
tens of nanometer2). These results activated several researchgroups and further progress in understanding formation
conditions and its effects on fusion plasma performance has
been made.㩷
In ITER, surface temperature of most of first walls
and plasma facing materials is about 200 C or less. Under
this temperature condition, tritium atoms are trapped at

Fig. 1. The dependence of incident ion energy E in for
bubble and hole formation on the PM-W surface irradiatedby low energy and high-flux He plasma.

Fig. 2. Surface morphology of SR-W before and after an
exposure to pure D plasma or D + He mixture plasma at D~51025 m-2, T s ~573K and c He+ ~20%..
1)D. Nishijima et al., J. Nucl. Mater. 313-316 (2004) 97.
2)S. Takamura et al., Plasma Fusion Res. 1, 051 (2006).
3)K. Tokunaga et al., J. Nucl. Mater. 337-339 (2005) 887.
4)M. Miyamoto et al., Nucl. Fusion 49 (2009) 065035(7pp).

2 16- 14

Fusion Power Reactor Design and Related Advanced Technologies
Category : Fusion Engineering/ Reactor Design
Year-Number :2000-FT6-2, 2001-FT6-06, 2003-FT64, 2004-FT6-2, 2005-FT6-3, 2006-FT6-1, 2007-FT62, 2007-FT6-4, 2008-FT6-2, 2009-FT6-1, 2009-FT63
Name: Y. Ogawa*, F. Najmabadi**, T. Goto*̐
Affiliation: *Graduate School of Frontier Sciences,
The University of Tokyo, **UC, San Diego (USA) (̐
National Institute for Fusion Science from FY2008)

In helical reactor designs, following the progress inexperiments of Large Helical Device (LHD) at NIFS, thedesign study of the LHD-type heliotron reactor FFHR has
been advanced in Japan. At present, optimization of plasma
parameters and design examination of superconducting coilsystems are in progress. The development of a systemdesign code for design window analyses also has been
advanced. In FY2008, a researcher from NIFS visited
UCSD and had discussions with members of the ARIES
Team. Improvement of reliability of the system code andestablishment of a common basis for comparison among
different design concepts are currently underway throughcrosschecking with the system design code for tokamaks
developed by ARIES. On the other hand, US carried out thecompact stellarator design ARIES-CS, which aims at higheconomic efficiency. There also reflects differences in theway of thinking between Japan and US.
In laser reactor designs, aside from KOYO and
KOYO-Fast reactor designs with a liquid wall chamber, thepossibility of a dry wall chamber design has been examinedin the fast-ignition laser fusion reactor (FALCON-D)
design study. The HAPL project in US also pursued thepossibility of a dry wall chamber. In 2007, a Japanese
researcher visited UCSD to discuss dry wall chamber
designs. The experimental results of helium irradiation ontungsten and repetitive pulsed heat load tests on the jointmaterial of tungsten – ferritic steel in US were applied tothe design study of FALCON-D. It was found that reduced
activation ferritic steel (RAFS) armored by ultra finegrained tungsten (UFG-W) can be a possible candidate forthe first wall of a fast-ignition laser fusion reactor [1].
Such crosscutting evaluations on multiple reactor
design concepts enabled the extraction of common issues
and deepened mutual understanding. For instance, common
problems exist between divertor / first wall in magnetic
fusion reactors and chamber technology in laser fusion
reactors. A quantitative comparison of heat loads on
divertors of magnetic fusion reactors and typical laser
fusion reactor chamber walls is shown in Table I.

To advance design studies of DEMO and commercial
reactors that follow after the ITER project, system optimization including the consideration of trade-offs between
fusion core plasma design and reactor engineering design is
indispensable. In these studies it is important to reflect
experimental results of present large-scale devices and theexperience obtained from the development of components
for ITER. The development of theoretical modeling andnumerical simulation codes is also a critical need. To provide an opportunity for information exchange and researchcooperation about these issues among Japan, US, EU andother countries including China, workshops and researcher
exchange programs have been carried out. The ARIES
Team, led by USCD in US, universities and institutes(NIFS, JAEA, CRIEPI) in Japan have engaged in these
activities. Several workshops were held with participantsfrom EU and China.
Reactor designs that were evaluated and comparedthrough these activities are summarized as follows:
TokamakJapan: SSTR, Slim-CS, DREAM, VECTOR, IDLT,CREST, Demo-CRESTUS:
ARIES-1 through ARIES-4, Pulsar, ARIES-RS,
ARIES-AT, ARIES-ST
Helical devices
Japan: FFHR series
ARIES-CSUS:
Laser fusion
Japan: KOYO, KOYO-Fast, FALCON-D
US:
HAPL, ARIES-IFE
In tokamak reactor designs, a major concern is thetrade-off between reactor economics and early realization,
resulting in differences among design concepts. US has
always emphasized economic competitiveness of thereactor, which leads to compact designs. US takes the
position that the COE of fusion reactors should be similar
to present power plants so that it can be introduced into themarket in competition with other energy sources including
fission reactors. On the contrary, Japan has emphasized
early realization and the promotion of public acceptancebased on several attractive points of fusion energy. It
exactly reflects the difference in the energy situation
between Japan and US. For comparison, EU aims at early
realization with a certain technology, and China pursues
fusion energy development with a view to fusion-fission
hybrid reactors, respectively.

Table I Comparison of heat loads on divertor in magnetic
fusion reactor (ITER) and typical laser fusion reactor
chamber wall.


1)

2 17
- 15

Goto, T. et al., Nucl. Fusion 49 (2009) 075006 (8pp).

Tritium Handling and Control Technology

Amount of Tritiated water [mCi/cm3]

Category : Fusion Technology
Year-Number : 2001-FT-6-5, 2002-FT-6-7, 2002-FT-6-8,
2003-FT-6-7, 2004-FT-6-3, 2005-FT-6-4
Name: Masabumi Nishikawa, Kenji Okuno*, S. Willms**,
C. Gentile***Affiliation: Kyushu University,*Shizuoka University**LANL, ***PPPLAt the time this program was initiated, activities intritium handling in US were focused on tritium handlingusing a large amount of tritium in TSTA and experimental
studies related to experiments at TFTR, and researchers
from JAERI took part in these activities as co-workers.
TSTA is now closed and has been decommissioned.
This program was started considering that the dataobtained in experiments using large amounts of tritium inUnited States national laboratories could be better
understood using analytical methods developed in basic
studies performed at Japanese universities. It is consideredby the author that research based on understanding abouttransport phenomena was important in the field of fusion
tritium research because the tritium system in a fusion
reactor consists of various continuous reactors such asplasma vessel, blanket system and fuel processing system.
At that time, however, there was no place to experiencehandling of a large amount of tritium in Japan, and there
were only a few tritium researchers interested in analysis
from the aspect of basic phenomena in the US. Then, it isconcluded that the co-operation must give good products
after discussion with some leading researchers in US.
It was recognized by several researchers in the US that
understanding the tritium transport phenomena in concretematerials was important because tritium contamination of
concrete walls in a tritium handling facilities is a serious
problem. It was also learned during discussion of thisprogram that some US tritiated waste is solidified withcement.
Then, the author started experiments to understand the
behavior of tritium in concrete considering that the overall
tritium behavior is explained by considering mass transfer
steps including adsorption, diffusion and isotope exchange
reactions.
The concentration profiles of tritium empiricallyobtained in concrete by the present authors are compared inFig. 1 with the estimated profiles using the model
constructed by the present author and his co-workers.
Fortunately, good agreement is observed in this figure.
Tritium release behavior from contaminated concrete walls
were calculated using our model as a function of tritium
concentration, chemical form of tritium, temperature andhumidity in air. The comments given by a researcher ofSavannah River to the simulation results is that thesimulation results given by the present model are similar tothe observations in their experience.

2.0

-2

Tritium conc. : 1.1×10 [PCi/cc]
48 hours after cutting samples

1.5

Exposed time & Total tritium
1.5 months 10.38[mCi]
1.0 month 6.80[mCi]
0.5 month 4.21[mCi]-92

leak flux : 2.11×10 [mol/m s]-5

KF,ex2=1.57×10 [m/s]

1.0

0.5

0.0

0

2

4
6
Cement paste length [cm]8

Fig. 1 Comparison of observed values and estimated values
for the distribution profile of tritium in concrete.
valuable empirical information from the Princeton Plasma
Physics Laboratory and the TSTA group at Los Alamos
National Laboratory on settlement, decommissioning,stabilization and surveillance of tritium contaminatedlaboratories or large tritium handling instruments andtechniques for waste management. Important information
for
training of new tritium researchers was alsotransferred. Such information together with analysis
performed by Japanese universities will be especiallyvaluable in Japan when a tritium handling laboratory is
closed in the future.
This program also gave us the opportunity to
exchange opinions about tritium fueling systems in the
future or in the ITER program with leading researchers in
Los Alamos National Laboratory, Savannah River National
Laboratory, Princeton University, Idaho National
Laboratory, and Rochester University as well as others.
Some information obtained in this program was utilized in
the Jupiter program and the Titan program.
The following are references about tritium behavior inconcrete walls generated by the present authors were
initiated from discussions in this program:
1) M. Nishikawa, K. Furuichi, H. Takata, “Study on
permeation behavior of gaseous tritium through concrete
walls,” Fusion Sci. and Technol.,50, 521-527(2006).
2) K. Furuichi, H. Takata, T. Motoshima, S. Satake, M.
Nishikawa, “Study on behavior of tritium in concrete wall,”J. Nucl. Mater., 350, 246-253(2006).
3) K. Furuichi, H. Takata, M. Nishikawa, et al.,“Evaluation of tritium behavior in concrete,” J. Nucl.
Mater., 360-370, 1243-1247(2007).

Through the information exchanges performed under
this program, the Japanese participants obtained much18

Second US/Japan workshop on target fabrication, injection and tracking
Category : Fusion Technology
Year-Number : 2002-FT6-5, 2003-FT6-2, 2003-FT68
Name: T. Norimatsu, D. Goodin,
Affiliation: Osaka University, General Atomics(USA),

the contamination of final optics in a reactor with wet wall
has also started. A preliminary experiment indicated that
deposition of metal vapor on the final optics can beprevented by filling low-pressure hydrogen gas in the beamduct.
Dan Goodin (GA) described the viability of an
economical target supply for IFE. He described proposed
target mass production processes and noted that target cost
reductions of 4 orders of magnitude are predicted. He notedthat the most difficult issue for direct drive targets is target
survival during injection. For indirect drive targets the mostdifficult issue appears to be target fabrication. Foam shells
with seal coatings are being developed by Schafer Corp.
High-Z coatings are being experimentally developed at GA.
DT layer smoothness is being measured and DT response to
rapid heating will be measured at LANL. GA isinvestigating layering in fluidized bed and other mechanicalmotion systems. GA has built an experimental target
injector in the newly refurbished building 22. GA andUCSD are calculating the effect of the high temperaturechamber on target survival.
Keiji Nagai (ILE) described the manipulation of the
microstructure of ultra-low-density TPX foams using
coagulant alcohol. Poly (4-methyl-pentene) cyclohexane
solution is mixed with boiled alcohol solution, gelled anddried with supercritical CO 2 . Depending on which alcohol
is used, foams down to 2 mg/cc are produced this way.
Rene Raffray (UCSD) described analyses of target
heating during injection. He noted highly reflective target
surfaces are needed to minimize radiation absorbed fromthe chamber wall.
Ron Petzoldt (GA) described the status ofexperimental target injection/tracking system. The system
includes a gas gun with an 8 m gun barrel and 17 m free
flight distance. Targets are protected in the barrel bysabots that use spring force for axial separation after thetarget leaves the gun barrel. A sabot deflector removes the
sabot and the target proceeds to target detectors that use
laser beams and line scan cameras to measure the targets
position. From preliminary target position measurements,
target downstream timing and trajectory are predicted inreal time. All major equipment for single shot operation is
now at GA and is being installed. A tour of the injector was
also provided.
T. Endo (Nagoya University) described a preliminary
conceptual design of target injector for fast-ignition laser
fusion and a small experimental accelerator. Hiroki
Yoshida (Gifu University) discussed target-tracking work at
Gifu University. R. Tsuji (Ibaraki University) described
the flying metal pipe for target protection in an IFE reactor.

The Second US/Japan Workshop on Target
Fabrication, Injection and Tracking (2002-FT6-5) was heldat General Atomics in San Diego, California on February 34, 2003. The purpose of this workshop was to allow
specialists in the areas of IFE target fabrication, injection,and tracking to exchange detailed technical information
specific to their work. The objectives of the workshop wereto disseminate detailed technical information, obtainknowledgeable peer review of results, and facilitate a soundscientific understanding of target issues. These objectives
were achieved in this very worthwhile workshop.
The following future invitations and actions wereplanned at the meeting.
1. The US is invited to ILE Osaka for the next workshop on
targets in September of 2004.
2. Abbas Nikroo (Head of the Center for Polymer andCoatings Development at GA) will visit ILE target labs in
April, 2003. (2002-FT6-2)
3. Japan will send Dr. Yoshida to the USA for an extended
stay in March of 2004 to work on tracking with our
injection demonstration system. (2003-FT6-8)
4. We will explore doing an injection demonstration with aJapanese fast ignition target on the US injection tracking
system.
The first day of the meeting emphasized target
fabrication and the second day target injection and tracking.
Mike Campbell (GA) welcomed the participants. Hispresentation emphasized advantages and special challenges
of fast ignition for IFE. He presented fast ignition concepts
for all drivers and gave recent experimental results fromboth the US and Japan. Potential advantages of fast
ignition include higher gain, reduced fabrication tolerances,and use of longer wavelength drivers which have higher
efficiency and smaller aperture requirements. Special
challenges include innovative cryogenic layering and 3-D
geometry with cones and shells.
Takayoshi Norimatsu (ILE) gave a broad overview
presentation on target fabrication and injection activities
leading to a laser fusion reactor with a wet wall[㧝]. This
includes work by many researchers on the reactor system,
lasers, plasma, and fueling. He described the roadmap (longterm research plan), requirements for injection and tracking
for both central hot spot and fast ignition, and this year㩟s
research activities. FIREX-I is a short pulsed laser
experiment that has been approved and is being
designed[ 㧞 ]. The follow-on FIREX-II experiment is
expected to demonstrate fast ignition and burn. They also
have plans to demonstrate repetitive laser illumination oftargets in the next few years. A simulation experiment on

References㧝T. Norimatsu, et al., Fusion Science and Technology, 52(2007 ) 893.
㧞
H. Azechi et al., Nucl. Fusion 49 (2009) 104024

2 19
- 17

20

CHAPTER 3

Fusion Physics Planning Committee (FPPC)

3.1 Objectives
The FPPC (Fusion Physics Planning Committee) is responsible for organizing US-Japan
collaboration on the experimental research of fusion plasma physics. In the initial phase of the
US-Japan collaboration, the experimental collaboration was planned and conducted to promotevarious concepts of fusion including fusion technology. The separation of the FPPC and FTPC
(Fusion Technology Planning Committee) was established in 1991. In order to study morecommon physics among different machines, since 1992, the collaboration has been conducted topromote plasma core phenomena, plasma edge behavior and control, heating and current drive,and new approaches and diagnostics development. After looking at the imbalance of the numberof activities among the categories, discussions on the possibility of the restructuring of thecategories were made for a few years. As a result, these categories have been restructured in2007 to the present status. The present subsections are now 1) Planning, 2) Steady-state
Operation, 3) MHD and High Beta, 4) Confinement, 5) Diagnostics, and 6) High Energy
Density Science. The physics of various concepts of magnetic and inertial confinement can be
discussed together by these subsections, which allows us to deepen the understanding ofcomplex behaviors of confined plasmas.

3.2 Activities
The collaborations are carried out by workshops and personal exchanges of researchers, by
keeping in mind that the number of the collaboration places should be balanced in US and Japanas much as possible. There were also collaboration activities using tele-video system and e-mail,although the number is quite small. During the years of 2000-2009 under US-Japan
collaboration, 285 workshops were conducted in USA and 528 researchers were sent to US on
various themes related to FPPC. In Japan, 141 workshops were held and 404 researchers weresent to Japan. These numbers are much increased compared the previous 20 years in which
period 14 workshops per year were conducted in USA and 32 researchers per year were sent toUS, and 11 workshops per year were held in Japan and 30 researchers per year were sent toJapan. The highlights of these activities are described afterward.

3.3 Administration
The present steering committee of FPPC consists of US DoE key-persons of FPPC and a person
in charge from Japan Atomic Energy Agency (JAEA) and a person in charge from universities
including National Institute for Fusion Science (NIFS) and 5 key-persons for 5 subsections fromJapanese universities. The steering committee of FPPC is also attended by the few relevant
observers from universities and institutes both in US and Japan, according to the necessity. As
for US-Japan universities collaboration, 5 key-persons from Japanese universities and NIFS are
designated for the promotion of collaboration in each subsection of FPPC. The last face-to-facesteering committee of FPPC was held at PPPL in April 2007, but it is usually held once a year
by a tele-video system.

21

3.4 Accomplishments and Highlights
3.4.1 Steady-State Operation
In the ITER era, one of the important research areas in fusion programs is steady state operationof the fusion plasma. The mutual collaboration of steady state operation covers the following
subjects; 1) plasma heating and current drive by RF waves, 2) improvement of the negative ion
based beam injection system, 3) Physics of plasma current start-up method, especially in
spherical tokamak, 4) control of the fluctuations in the SOL and related plasma wall interaction,5) suppression of the fast events in steady state operation. The topics are:1) Collaboration of “Plasma heating and current drive” has been performed seven times asworkshop from 2000 to 2009. Total number of participants and presentations are 193 persons
and 169 topics, respectively. In the experimental area ECH and ECCD, LHCD, HHFW and ICH
results have been presented from 8 devices in Japan and 5 in US. EBWCD in sphericaltokamaks and LHD becomes recent highlight. Long pulse operation > 5 hours in TRIAM-1M
and the current drive with the order of MA in C-mod and JT-60U demonstrated the usefulness of
LHCD. Steady state operation in LHD was also achieved by ICH and energetic particles physics
is also recent topics. In the theoretical area, benchmark test among various RF physics codes are
expected in the collaboration works.
2) Collaboration of “Negative ion based NBI system” has been done between NIFS and PPPL
from 2000 to 2007. Two important developments related to long pulse operation of the Cs based
NBI system are a) time evolution of beam H fraction with Doppler shift spectroscopy and b)
real time measurement of Cs consumption and tungsten filament. Using Doppler shifted
spectroscopy the life time of beam component at the full energy is monitored up to 70 sec. The
beam uniformity for various Cs consumption rate is measured and analyzed from the viewpointof beam life time.
3) Collaboration with “Wave physics” including current start-up has been carried out from 2000
to 2009 by University of Tokyo, PPPL, and MIT PSFC. Topics related to this category covered
HHFW heating and current drive, solenoidless current ramp-up, TORIC simulation, and LHCD
and start-up. In this collaboration test of start-up scenario in ST is common interest.
Collaborated experiments about the HHFW and solenoidless start-up were succeeded in NSTX
and TST-2. LHCD start-up experiments in MIT showed the higher density limit in LHCD at 4.6
GHz. Current hole experiment aiming at high bootstrap fraction is planned in MIT.
4) Collaboration of “SOL physics and PWI” has been done as personal exchange and workshop.
The former is focused on the non-diffusive transport and related dust production. Using a steadystate linear device blob generation was studied in a high density plasma under the attached ordetached conditions. The latter aims at discussing about plasma surface interaction of high Z
materials from both microscopic and macroscopic viewpoints directed towards understanding ofsteady state operation.
5) Collaboration of “merging and magnetic reconnection” has been performed as workshop
from 2000 to 2009. This collaboration among solar, magnetosphere and laboratory scientists
helps mutual understanding of the observations and creates common physical view associatedwith the same physics. Based on the collaboration, a new project; Center for magnetic
Self-organization in Laboratory and Astrophysical Plasma has been accepted by US NSF and
JSPS. Collaboration with fusion plasma scientists is expected to suppress the fast events
disturbing steady state operation.

22

Workshop on Physics of RF Heating and Current Drive
Category: Fusion Physics/ Steady-State Operation
Year-Number: 2000-FP4-6, 2003-FP4-2, 2004-FP4-1,
2005-FP4-2, 2006-FP4-1, 2007-FP2-3, 2008-FP2-4, 2009-FP2-1
Name:
R.Kumazawa,
T.Watari,
Y.Takase1),
2)
3)
4)
M.Ichimura , S.Kubo, J.Hosea , R.Prater
Affiliation:
National
InstituteforFusionScience, 1)Tokyo Univ., 2)Tukuba Univ., 3)Princeton
PlasmaPhysics
Laboratory(PPPL), 4)General
Atomic(GA)The increase of 6keV via TTMP process in theelectron temperature was achieved with the HHFW heatingof 3MW on NSTX. However a degradation of the heating
efficiency at the lower NI had been reported. It was
conjectured as the cause that the HHF wave was able topropagate as the LHW in the scrape-off plasma. Then the
reduction of the scrape-off plasma density employing
Lithium coating method improved the heating efficiency at
the lower NI.
4) ICH: Ion cyclotron heating
A remarkable progress was achieved on LHD. The
plasma was sustained with only the ICH power. The
plasma parameters were the same that produced with NBI.
The plasma was sustained for one hour, which is one of themain objectives on LHD. A good confinement of highenergy ions with more than 1MeV was confirmed during
the long pulse discharges. A plasma production and heating
using a folded waveguide antenna was first succeeded. Thisantenna was designed and fabricated with the collaborationof ORNL.
A high RF power injection up to 6MW was achieved
using three antenna sets on C-Mod. It is interesting that
there was no difference of the heating efficiency in the RFphase between antenna straps. It is very surprising that theion cyclotron wave converting from the fast wave was firstobserved using a phase contrast image (PCI) method. It
mainly owed to the progress in the wave analysis of
AORSA code as later described.
[Theory]
A big budget was invested to develop the research
about RF wave physics in USA. There is a big difference inthe number of researchers between USA and Japan, but theJapanese activity is almost equal to that in USA.
Codes of AORSA, TASK and TORIC were based
and other codes were combined to them to analyze theplasma heating and the current drive. For example those are
AORSA-CQL3D, TORIC-CQL3D, AORSA/TORICGENRAY and TASK/WM-FP etc.
The results obtained using a combination code are as
follows: A velocity distribution of high-energy ions during
ICRF heating was calculated using combined codes, e.g.,
TASK/WM-FP, GNET-TASK/WM and ORBIT-RF/
AORSA. The WM code is a code calculating the wave
dispersion relation and the FP code is for calculating anenergy distribution using Fokker-Planck equation. GNET
code is a 5D simulation code. ORBIT code is also 5D code.
It should be noted that codes of TASK/WM and AORSA
could calculate the RF electric field including high-energyions.
At the first step an initial dispersion relation was
calculated using the bulk plasma parameters, then avelocity distribution of high-energy ions was calculatedusing FP code with the initial RF electric field. At the next
step the wave dispersion relation including a high-energy
ions was calculated and the velocity distribution of highenergy ions was determined using FP code with a new RF
electric field. Then the distribution of high-energy ions wasconverged after several iteration processes.

Workshops on physics of RF heating and current
drive were held seven times in the decade. Total number ofparticipants and presentations are 193 persons and 169
topics, respectively. Remarkable results in the experimentand the theory are described as follows.
[Experiment]
Experiment devices:Japan: LHD, JT-60U, LATE, TST-2, H-J, TRIAM-1M,
GAMMA-10, QUEST etc.
USA: DIII-D, Alcator C-Mod, NSTX, HSX, MST etc.
Experimental results obtained on the above devices
are reported in four categories of different appliedfrequency, i.e., ECH and ECCD, LHCD, HHFW, and ICH.
1) ECH and ECCD: Electron cyclotron heating and current
drive
A high electron temperature of 15keV at the axis of
LHD was achieved with the power of ECH about 3MW,
even in the low electron density of n e =2x1018m-3. A power
absorption profile could be precisely known employing thepower modulation method and it agreed with thenumerically obtained one using a ray tracing method. In
addition X-B and O-X-B heating was tried and was verified
to be an effective heating method. Recently a collective
Thomson scattering method was started to measure an ionenergy distribution using an existent ECH system.
An NTM was suppressed using ECCD on DIII-D and
JT-60U, which resulted in the observable improvement ofplasma parameters. On the other hand a radial profile of
ECCD was measured with MSE on DIII-D. It wascompared with the data using a combined code of TORICGA and CQL3D as described later and the physics of
ECCD was clearly understood.
Experiments of a plasma current startup weresuccessfully carried out on LATE and TST-2. In addition
recently the experiment was started on QUEST and thecurrent drive using O-X-B will sustain the plasma for longtime.
2) LHCD: Lower hybrid current drive
The plasma discharge for more than 5 hours wasachieved on TRIAM-1M. A full current drive operation
was carried out on C-Mod with a domestic collaboration of
PPPL, i.e., 1MA at n e =5x1019m-3 using 1.2MW at
f=4.6GHz.
A current profile control for ITB formation was
succeeded on JT-60U using MSE measured signal. In
addition it is worth to note that the plasma current startup
was successfully carried out using LHCD power on JT-60U.
3)HHFW heating: Higher harmonic fast wave heating

323-3

Improvement Studies of Negative-Ion-Based Neutral Beam Injection System

Intensity (arb.)H

W(full E)
alpha

4000
3000
2000
1000
0
655

The LHD was the only machine that relied uponnegative ion-based neutral beam injection system, N-NBI,
as the principal heating power source, which applied highpower cesium-seeded negative hydrogen ion sources as one
key device. Leading objective of the collaboration study
was an improvement of the system of N-NB, beam physics
study, and the beam heating /operation-method with highpower (15MW) long pulsed N-NBI for LHD and possibly
ITER plasmas in future. These, founded on main part ofstudy, by NIFS, of the high current negative ion source /heating for the full specifications had been done incollaboration with PPPL which had experiences on positive
deuterium NB system at high power level of ~30MW, andalso JAEA on beam spectrometer system.
The principle fruits of this collaboration studies were
Doppler shift measurements. The beam velocity distribution(Fig.1) were observed systematically with Doppler-shift
Halpha spectroscopy on large area negative ion sources ofstandard LHD-N-NBI system, observing the time evolution
for injection pulses as long as 128sec of record value, andthe stripping spectrum from beams with single stage
accelerators [1, 2]. Full energy component (intensity) of thenegative ion beams decreased with time (Fig.2). The beam
uniformity appeared to vary with time during one pulse
duration. It was attributed to the variation of Cs migrationon the plasma grid and/or the Cs recycling, and thestripping losses in the acceleration gap of the ion source.
These validated that the spectroscopy was useful tool as a
non-interfering beam monitor during high power NB
injection shots for the LHD and the ITER under radiation
circumstances. In the next place of the fruits, much progress
on beam injector operation and maintenance of powerfullong pulse N-NBI was achieved by analysis ofmeasurement of Cs consumption (Table I) [3], weight loss
(lifetime) of tungsten filament, and the power
deposition/energy spectrum of co-accelerated electron
beam component (Fig.3) [4] as well as the beam blocking
study in N-NBI.
Table I.

sn48046

5000 Unshifted

Category : Fusion Physics/ Heating
Year-Number : 2000-FP4-4,2001-FP4-04,2003-FP41,2004-FP4-2,2005-FP4-1,2006-FP4-2,2007-FP4-2
Name: Y. Oka, L. R. Grisham*Affiliation: National Institute for Fusion science,*Princeton Plasma Physics Laboratory (USA)

W(Vext)660
665
Wavelength (nm)670

Fig.1 Doppler shift spectrum in Halpha light of the LHDNNBI beam.

sn48818

Intenssity (arb.)

5000
4000
3000
2000

VUGE








1000
0
661.5

#5

662

#3-c

#1

662.5
663
Wave length (nm)663.5

Fig.2 Temporal profile for full energy beam component
for 74 s long pulse injection(sn48818).
Vfull=95 kV, Iacc=14A(IS-2B).

Fig.3 Temperature-rise profile on the dump for coaccelerated electron beam component with LHD-NNBI
full-size(1/1) and 1/3rd-negative ion sources.
1) Y. Oka et al., Rev. Sci. Instrum. 77(2006)03A538
2) Y. Oka et al., Rev. Sci. Instrum. 79(2008)02C105
3) Y. Oka et al., Rev. Sci. Instrum. 75(2004)1803
4) Y. Oka et al., Rev. Sci. Instrum. 73(2002)1054

Tungsten filament weight loss and Cesium weight loss for LHD ion sources24

Intermittent bursty plasma transport in attached- and detached-plasmas
Category : Physics (edge plasmas)
Year-Number : 2002-FP3-03, 2003-FP3-18
Name: N. Ohno*, S. Krasheninnikov**Affiliation: *Nagoya Univ., **UCSDIntermittent convective plasma transport acrossmagnetic field lines, “Plasma Blobs” has been one of themost important issues in fusion-related edge plasma
physics, and is thought to play a key role for cross-fieldplasma transport in the tokamak scrape-off layer. Several
experiments have been performed regarding blobby plasmatransport, in which intermittent bursts of fluctuation in ion
saturation currents measured by Langmuir probes wereanalyzed to obtain a basic property of the blob’s motion.
Such bursty fluctuation has been also observed in otherplasma devices. Then, the blobby plasma transport isthought to be common phenomena in magneticallyconfined plasmas.
We investigated the intermittent convective plasmatransport in a attached and/or detached plasma condition of
the linear divertor plasma simulator, NAGDIS-II. The
NAGDIS-II can generate high density helium plasmas with
an electron density up to 1020 m–3 in a steady state. The
diameter of a plasma column is about 20 mm. By
increasing neutral pressure P in the divertor test region, we
can achieve a detached plasma condition. Ion saturation
currents Isat were measured with a Langmuir probe. Imagesof light emission from a plasma were taken by the fastimaging camera located at the end of the vacuum chamber.
Images taken by a fast-imaging camera clearly show that in
attached plasmas, blobs are peeled off the bulk plasma, andpropagate outward with an azimuthal motion. In detachedplasmas, plasma turbulence observed near the plasma
recombining region drives strong intermittent radial plasmatransport, which could broaden the radial density profile.
Figure 1 shows the time evolution of the ion
saturation current Isat measured at the periphery (r = 60mm) in the downstream. Many positive spikes in Isat wereobserved. As P is increased to produce fully detachedplasma, positive spikes in Isat, which is related to be theplasma blob observed by a high-speed camera, becomeswider and their amplitudes increase. Then, the averaged
value of Isat increases with P at r = 60 mm as shown in Fig.
2, although the averaged Isat at the center of the plasma
column dramatically drops. These experimental results
indicate that the plasma blobs due to the instability in the
detached plasma drives strong convective radial transport,
which leads to a broadening of the plasma profile. This
could play an important role in the reduction of the particle
and heat flux to the divertor plate as well as the plasma
recombination processes in plasma detachment.

Fig. 1 Neutral pressure dependence of time evolution of I sat at r = 60 mm.

Fig. 2 The averaged value of I sat and fluctuaion level as a function ofneutral pressure P.

1) N. Ohno, K. Furuta, S. Takamura, Journal of Plasma
Fusion Research, Vol.80, No.4, 2004, pp.275-276.
2) N. Ohno, V. P.Budaev, K. Furuta, H. Miyoshi, S.
Takamura, Contributions to Plasma Physics, Vol.44, No.13, 2004, pp.222-227.

325-5

Study of dust transport in fusion devices
Category : Physics (edge plasmas)
Year-Number : 2006-FP3-3
Name: N. Ohno*, S. Krasheninnikov**Affiliation: *Nagoya Univ., **UCSDDust particles have been found in magneticallyconfined fusion devices. The dust particles could be
generated due to strong plasma-wall interaction, and betransported into core plasmas. Such dust particles would
not pose serious problem on safety and operational issues
in present devices, however, in future devices such as ITER
(International Thermonuclear Experimental Reactor), dust
particles could be serious problem because dust formationin the next-step devices is expected to increase by several
orders of magnitude due to long pulse operation. Dust
accumulation inside the vacuum vessel contributes to huge
tritium inventory. In addition, dust penetration into the coreplasma could cause degradation of plasma performance anddisruption.
Comprehensive study of dust formation and transport
becomes one of the most critical issues in fusion plasma,
however, few experiment of dust transport has conducted
and our present knowledge of the mechanism of transportof dust particles in fusion devices is rather limited. In order
to control the dust transport, it is necessary to clarify
dominating forces acting on dust particles in fusion devices.
In large fusion devices, it's difficult to investigate asystematical study of dust transport because no one knows
the size and the mass of dust particles transported in thedevices. Then, we need to conduct the dust transport
experiment by using given dust particles in high density
deuterium plasma relevant to edge plasma condition offusion devices.
We have investigated dust particle transport in highdensity deuterium plasma with toroidal divertor
configuration by using toroidal divertor plasma simulator
NAGDlS-T (NAGoya D1vertor plasma Simulator with
Toroidal magnetic configuration). Carbon dust particles,
are set on Piezoelectric vibrator installed from bottom of
the vacuum vessel. Dust particles are illuminated by the
halogen lamp and their motion was measured by using
high-speed camera as shown in Fig.1.
It is found that the dust particles were transported
radially across the magnetic field. The direction of the dust
motion depends on the direction of toloidal magnetic field(Fig. 2). Figure 3 shows calculated forces acting on a dust
particle in plasma. It is found that a friction force between
an ion flow and a dust particle is much larger than otherforces, electrostatic and gravitational force in theexperimental condition. Therefore, the friction force is adominating one. This calculation indicates that the dust
motion in Fig. 2 is mainly detemined by diamagnetic ion
flows in front of the piezoelectric vibrator.

Fig. 1 Experimental Setup.

Fig. 2 Dust transport depending on direction of magnetic field.

Fig. 3 Dependence of force acting on a dust particle on its radius.

1) N.Ohno, M.Yoshimi, M.Tokitani, et al., Journal of
Nuclear Materials, 390-391 (2009) 61-64.
2) Takashi Yamada, Noriaki Matsui, Noriyasu Ohno, etal., Int. Symp. on EcoTopia Science, 2007, Nagoya,Japan3) Takashi Yamada, Noriaki Matsui, Kengo Yada,
Noriyasu Ohno, Makoto Takagi, 8th Workshop on
Fine Particle Plasmas, 2007, Toki, Japan

26

3.4.2 MHD and High Beta
The first US-Japan MHD workshop on Active Control of MHD Mode in Toroidal Plasmas was heldin San Diego in conjunction with the 3rd US MHD meeting in November 1998. Since then, the
US-Japan MHD workshop has been held annually. In these US-Japan MHD workshops, useful
research information is exchanged, and a variety of MHD control issues are discussed. In order toachieve steady-state high-beta tokamak operation it is necessary to stabilize various instabilities,
especially the neoclassical tearing mode (NTM) and the resistive wall mode (RWM). Common
MHD issues of tokamak and helical plasmas were discussed, and the importance of 3D effects on
plasma control physics was clarified.
Rotating magnetic field (RMF) current drive, a steady-state current drive method for field-reversed
configuration (FRC) originally developed on Rotamak, was developed further on the much larger
TCS device at the University of Washington. A new RMF current drive system was developed for
the FIX device at Osaka University with assistance from the TCS group. The RMF antennas in thissystem, located inside the metal flux-conserving vacuum vessel, kept the sustained FRC plasma
away from the plasma wall. Efficient formation of an oblate FRC with a large amount of magnetic
flux can be achieved by counter-helicity merging of spheromaks. Various collaborative experimentson counter-helicity plasma merging, which results in high-beta FRC formation, were conducted on
the MRX device at PPPL. Equilibrium and stability of the FRC plasma was studied, including therole of the Hall effect during counter-helicity merging, global stability of oblate FRC, andsustainment by the central solenoid.
Fast-ion-driven MHD instabilities such as the energetic particle continuum mode (EPM) and the
Alfvén eigenmode (AE) could induce anomalous transport of fast ions/alphas in D-T burning
plasmas. A scintillator-based lost-fast-ion probe (SLIP) was first installed on CHS, andsubsequently two SLIPs were installed on LHD in collaboration with PPPL to detect lost fast ionswith gyroradius and pitch angle resolution in the presence of EPM/AE. Recurrent bursting
magnetic fluctuations (most likely EPMs) are often observed in LHD when a low density plasma isheated by tangential NBI. Fast ion losses correlated with EPM bursts were detected by SLIP,
indicating that the EPM causes spatial redistribution and loss of beam ions.

327-7

MHD Stability Control of Toroidal Plasmas
Basic Processes of Active MHD Control
Seven researchers from Japan attended it, and totally
about 40 talks were presented in the workshop
including several European researchers. The
memorial talk for two late distinguished MHD
researchers, Anders Bondeson and Torkil Jensen, waspresented. The main sessions of the workshop are“modelling feedback, resistive wall modes (RWMs)”(Ref.2), “non-axisymmetric devices”, “plasma
response to non-axisymmetric fields”, “ballooning,
neoclassical tearing modes (NTMs) and other” and“active control experiments”. The summary and nextyear planning (US domestic Workshop in the
University of Wisconsin and US-Japan Workshop in
JAERI) were discussed on the final session.
In these US-Japan MHD workshops, useful
research information exchange was performed among
Japan, US and EU, and a lot of MHD control issues
of tokamak, helical systems and RFP were discussed.
Especially, the common MHD issues of tokamak andhelical plasmas (TABLE I) was discussed, and theimportance of 3D effects on plasma control physics
was clarified in these workshops.
The above description is based on 2003 and2004 collaboration researches. In 2010, the 13th USJapan workshop will be held in the University of
Wisconsin. The reason why we can continue our
MHD workshop for a long time might be due tosynergetic effects between US-side Tokamak-relevant
control researches and Japan-side broad research
programs. Especially, 3-dimensional effects in MHD
tokamak control physics become rather important.
The part of the research achievement of thisworkshop will be published in the Journal PPCF
(Plasma Physics and Controlled Fusion) as a special
issue of Active MHD Control.

Category : Fusion Physics/ Core Plasma Phenomena
Year-Number : 2003-FP2-2, 2004-FP2-9
Name: Kozo Yamazaki, Takahisa Ozeki
Michio Okabayashi, Gerald Navratil
Affiliation: National Institute for Fusion Science(Present: Nagoya University)
Japan Atomic Energy Research InstitutePrinceton Plasma Physics Laboratory
Columbia University  For the achievement of high performance
toroidal plasmas, it is necessary to stabilize various
instabilities. Especially, relevant to steady-state highbeta operation of tokamaks, the stabilization of RWM(Resistive Wall Mode) and NTM (Neoclassical
Tearing Mode) is one of main research issues. As for
feedback-control plan of tokamak plasma instabilities,
FSX (Feedback Stabilization Tokamak) project was
discussed in 1996, and extended to the nonaxisymmetric magnetic field application and
ECH/ECCD stabilization experiments at Columbia
University (HBT-EP) and GA (DIII-D) reported in
the first US-domestic MHD meeting. The first USJapan MHD workshop on ‘Active Control of MHD
Mode in Toroidal Plasmas’ was held in San-Diego
combined with the 3rd US-domestic MHD meeting.
As an extension of this workshop, the 6th
MHD Workshop on “MHD Stability Control of
Toroidal Plasmas” was held in Naka JAERI, Feb.2-4,
2004. This was the 5-day joint workshop combinedwith the Large Tokamak workshop on “Physics ofCurrent Hole” (W56) and the Fourth meeting of the
ITPA (International Tokamak Physics Activities)
Topical Group on MHD, Disruption and Control.
Within the US-Japan workshop, totally more than 30
talks, including JT-60U, LHD, NSTX, NCSX, DIII-D,
Alcator C-Mod, ASDEX-UG, ITER results, were
presented. The sessions of the workshop are “stability
in helical system and control (Ref.1)”, “stability ininnovative confinement concept”, “non-ideal andnon-linear MHD stability behavior”, “neoclassicaltearing mode and steady state issues”, and“stabilization and destabilization by wall, error field,
rotation and others”.
Moreover, the 7th US-Japan MHD Workshop
on “Basic Processes of Active MHD Control” washeld in Princeton Plasma Physics Laboratory, during
November 21(Sunday)-23(Tuesday), 2004, just after
the American Physical Society Meeting. This wasorganized as both US-Japan Workshop and 9th USdomestic Workshop on MHD Stability Control.

TABLE I Operational limits in tokamak and helical systems[from Ref.1]

1)
2)

328
-8

Yamazaki, K., Kikuchi, M., J. Plasma Fusion Res.
SERIES, Vol.5 (2003) pp 28-35.
Okabayashi , M., et al, Nucl. Fusion 45 (2005) 1715

Steady Current Drive and Efficient Formation of High-beta FRC Plasmas
Category : Fusion Physics/ MHD and high-beta
Year-Number : 2001-FP2-20, 2005-FP4-5
Name: M. Inomoto, A. Hoffman*, M. Yamada**
Affiliation: Osaka University, *University ofWashington, **Princeton Plasma Physics Laboratory

Different from the conventional theta pinch method
which has difficulty increasing the trapped magnetic flux,
the counter-helicity merging of spheromaks provides
efficient formation scheme to provide an oblate FRC withlarge amount of magnetic flux. Thus the oblate FRC plasma
produced by the counter-helicity merging is expected astarget plasma of the neutral beam injection heating. In thiscollaborative program, we carried out various experimental
researches on the counter-helicity plasma merging andresulting high-beta FRC formation in MRX device at
Princeton. The main research contents were thecontribution of the Hall effect on the counter-helicity
merging, global stability of the oblate FRC, sustainment by
the center solenoid coil, and so on. Typical example of theHall effect is summarized in Fig. 2. Radial inward/outward
displacement of X point during merging was observed
according to the toroidal field polarities of initialspheromaks. A simple Hall-MHD model illustrates that thisX-point motion corresponds to the quadrupole out-of-planemagnetic field caused by the Hall effect in collisionlessreconnection, in which the Hall electric field enhances thereconnection rate. We also observed that the outflow
structure was modified due to the pressure change on thedownstream region which is caused by the global change ofthe magnetic field. The polarity of the counter-helicity
merging also brings about the changes of density andtoroidal flow profiles of the FRC plasma, indicating that the
combined effect determines the equilibrium and stability of
the FRC plasma.

Collaborative researches on steady current drive method
using rotating magnetic fields (RMF) and on efficient
formation method using counter-helicity merging of
spheromak plasmas were carried out to expand thecapability of the field-reversed configuration (FRC)
plasmas. The FRC is a high-beta plasma confined solely by
the poloidal magnetic field and is suitable as a reactor coreplasma for advanced fuel nuclear fusion, nevertheless,experimental studies on improvement of confinement havebeen hindered because of (a) lack of promising heating /current drive methods and (b) difficulty on producing FRC
plasma with large trapped magnetic flux.
Steady current drive method using RMF has beendeveloped to solve the former issue. FRC current driveusing RMF was demonstrated on rotamak device at
Flinders University and then larger experimental apparatusof the TCS device was constructed at University ofWashington. With great efforts of the TCS researchers, wedeveloped a new RMF current drive system on the FIX
device at Osaka University. Major difference from theprevious experiments was that the RMF antennas in oursystem were located inside the metal flux-conserving
vacuum vessel. This new RMF method conduced to keep
the sustained FRC plasma away from the plasma wall
because of the preferential penetration of the RMF. Fig. 1
shows the typical waveform of RMF discharge on the FIX
device. The internal field reverses just after the applicationof the RMF, forming FRC plasma with about 1ms duration.
The ratio of the separatrix radius to the wall radius is about
62%, which is rather smaller than those observed in theother devices.

(a) t=240Ps

RMF current [kA]
Bz [G]

10
0.5
0r [cm]

30
0-10

z [cm]

10
electron
flow

20

jreco
jreco

antenna Az(a)(c) Case I

electronflow

Case OBz (r = 0.25m)

Fig. 2. Poloidal magnetic flux contours (solid lines) withpoloidal magnetic field (arrows) and toroidal magnetic field(color coded) at t=240 Ps (a) and at t=260Ps (b) in cases I(left) and O (right) counter-helicity merging, andcorresponding three-dimensional illustrations of reconnecting
field lines in the Hall-MHD regime (c) [2].

0Bz (r = 0)

-10 (b)0.3
R, r'I [m]0
Bt [mT]

r

10

r'I

0.2
0.1

Case O35

shot: 54801

antenna B

Case I

40

-20

0.5

(b) t=260Ps

Initial state

R

(c)

0
0

0.5

1
time [ms]

1.5

2

1)
2)

Fig. 1. Time evolutions of (a) RMF antenna currents, (b)axial magnetic field, and (c) separatrix and major radii [1].

329
-9Inomoto, M., et al., Phys. Rev. Lett. 99 (2007) 175003
Inomoto, M., et al., Phys. Rev. Lett. 97 (2006) 135002

Energetic-ParticleDiagnostic
Diagnosticinin thethe Large
Large Helical
Energetic-Particle
HelicalDevice
Device(LHD)(LHD)
Category : Fusion Physics/Phenomenon in ReactorRelevant Plasma
Year-Number : 2003-FP2-4
Name : Mitsutaka Isobe, Douglass S. Darrow*
Affiliation : National Institute for Fusion Science,*Princeton Plasma Physics Laboratory

points are dispersed across the orthogonal dimension of thescintillator according to their pitch angles.
Recurrent bursting magnetic fluctuations which aremost likely EPMs are often observed in LHD when NBs
are tangentially injected into relatively low density plasmas(ne~1x1019 m-3).
Fig. 2 shows time traces of theamplitude of magnetic fluctuations filtered in frequency of
10~40 kHz, fast-neutral flux measured with E//B-NPA
oriented so as to detect fast-neutral particles chargeexchanged with co-going beam ions, beam-ion loss rate to
SLIP placed at the outboard side and stored energy
evaluated from a diamagnetic loop signal. In this shot,
volume-averaged beam ion β is comparable to the bulk
plasma β. Correlated with each EPM burst, fast-neutral
flux (E~148 keV, χ < 40 deg.) and beam ion loss rate to the
SLIP significantly. E and χ of detected escaping beamions are ~160 keV and ~30 deg., respectively and areconsistent with energy of anomalously transported beamions measured with E//B-NPA. This observation tells that
there exist co-going beam ions redistributed toward the
peripheral region at the outboard side and some oftransported beam ions are lost due to EPMs.

Fast-ion-driven MHD instabilities such as energeticparticle continuum mode (EPM) and Alfvén eigenmode(AE) are of great concern in current fusion plasma
experiments because those instabilities may lead toanomalous transport of fast ions/alphas essential inmaintaining self-ignited state in a future D-T burning
plasma. Alfvénic modes destabilized by fast ions are
regularly observed in tokamak plasmas with strong, superAlfvénic ion tails.
They are also destabilized inheliotron/stellarator plasmas.
In helical plasma
experiments, the confinement of magnetically trapped fastions has been so far one of key arguments because of thesymmetry breaking of the system. It must be noted thatthe issue related to trapped-ion orbit in a three-dimensional
magnetic field configuration is currently being solved as aconsequence of numerous efforts in optimizing
configuration. However, a great deal of attention shouldbe paid to redistribution and/or losses of fast ions induced
by energetic-ion-driven MHD instabilities because theinterplay between fast ions and fast-ion driven MHD
instabilities is not fully understood yet. To predict what
will happen in fast-alphas-driven burning plasmas andfurthermore, to explore possible discharge scenarios that
can avoid serious events associated with fast ions,
phenomena caused by fast ions in existing experiments
should be carefully investigated.
Scintillator-based lost-fast ion probes (SLIP) arebeing employed in the Large Helical Device (LHD) todetect lost fast ions while EPM/AE are destabilized due totangentially injected beam ions. The SLIP was originallyproposed and developed in Princeton Plasma Physics
Laboratory (PPPL) to study loss process of MeV fusion
products, beam ions and fast ions accelerated by ICRH [1].
A project of the SLIP in National Institute for Fusion
Science (NIFS) was initiated in 1997. Dr. D.S. Darrow of
PPPL who has a thorough knowledge of the SLIP wasinvited to NIFS as a visiting professor for about one year.
As a result of his great contribution, the SLIP was
successfully installed onto CHS [2]. Subsequently, Dr.
Darrow visited NIFS in the framework of Japan/U.S.
Cooperation in Fusion Research and Development, helping
us in transferring the SLIP technology to LHD. At
present, LHD is equipped with two SLIPs at inboard andoutboard sides of the torus.
Fig. 1 depicts basic functions of SLIP. The SLIP isbased on a magnetic spectrometer concept, providing
gyroradius and pitch angle (χ=arccos(v///v)) of escaping
fast ions as a function of time. As seen in Fig. 1, ionswith larger gyroradii strike the scintillator farther from theapertures than those vdth smaller gyroradii. Their strike

Fig. 1. Basic function of scintillator-based lost fast
ion probe.

Fig. 2. Time traces of δBEPM at the Mirnov coilposition, charge exchange fast neutrals for threedifferent particle energies, beam-ion loss rate to SLIP
(E~160 keV, χ~30 deg.) and Wp.
1) Zweben, S.J., Nuclear Fusion 29 (1989) 825.
2) Isobe, M. et al., Rev. Sci. Instrum. 12 (1999) 4589.
3) Isobe, M. et al., Fus. Sci. Technol. to be appeared inJuly 2010.

3 30
- 10

3.4.3 Confinement
The mutual collaboration of confinement physics experiments has been developed between US andJapan. One example is the US-Japan personal exchange program related to the coaxial helicity
injection (CHI) experiment on National Spherical Torus Experiment (NSTX) of Princeton Plasma
Physics Laboratory (PPPL) and Helicity Injected Spherical Torus (HIST) of University of Hyogo.
The purpose of this US-Japan collaboration is to investigate potential of application of the CHI
current drive and start-up methods to Spherical torus (STs). The related experiments were successful
and the studies moved to the transient CHI experiments. These results also demonstrated thepotential for the application of this method to future machines. With regard to NSTX, anotherexperimental collaboration of the plasma current ramp-up by vertical field was conducted and theobtained results were transferred to the domestic confinement experiment of QUEST at Kyushu
University. A series of US-Japan experimental collaborations concerning radiofrequency (RF) wave
physics on tokamaks, including spherical tokamaks (ST), were carried out with the groups atUniversity of Tokyo, PPPL and Massachusetts Institute of Technology Plasma Science and Fusion
Center (MIT PSFC). Remote execution of experiments from Japan to PPPL were carried out
successfully. In this collaboration, the start-up experiment was carried out over two years withsuccessive improvements. However, while plasma initiation was achieved, but not Ip ramp-up. At
MIT, heating and current drive experiments by the ICRF fast wave and the lower hybrid wave
(LHW) were carried out on the high field tokamak Alcator C-Mod.
From the viewpoint of plasma confinement theory, the US-Japan collaboration study of the two-fluid
low-collisionality equilibrium model and its application to rapidly-rotating high-performance
spherical torus was carried out with the group of Niigata University in Japan and the NSTX group at
PPPL. The calculation results were found to be markedly different from static or slowly flowing
equilibrium.
US-Japan workshop on Physics of Plasma Merging and Magnetic Reconnection has been held todiscuss recent progress in physics and applications of plasma merging/magnetic reconnection. The
first MR workshop MR2000 was held at University of Tokyo in Japan and, after MR2000, theMR200X workshop have been held by 50-60 invited and contributed speakers every year either in
US or in Japan. Based on these activities, a new reconnection and dynamo COE project: Center for
Magnetic Self-Organization in Laboratory and Astrophysical Plasmas was accepted by the US
National Science Foundation (NSF) in 2008 and by Japan Society of the Promotion of Science(JSPS) in 2010, which are now exploring a new stage of US-Japan collaboration on magnetic
reconnection and self-organization caused by reconnection. On the other hand, the first US-JapanMHD workshop on Active Control of MHD Mode in Toroidal Plasmas was held in San-Diego
combined with the 3rd US-domestic MHD meeting. As an extension of this workshop, the 6th MHD
Workshop on “MHD Stability Control of Toroidal Plasmas” was held at Naka JAERI in 2004. The
7th US-Japan MHD Workshop on “Basic Processes of Active MHD Control” was held at PPPL in
2004. In these US-Japan MHD workshops, useful research information exchange was performed
among Japan, US and EU, and a lot of MHD control issues of tokamak, helical systems and RFP
were discussed.

3 31
- 11

Coaxial helicity injection (CHI) start-up and current drive for ST plasmas
Category : Fusion Physics/ High beta, Heating andcurrent drive
Year-Number : 2000-FP4-9, 2001-FP4-07, 2003FP4-5, 2004-FP4-3, 2006-FP4-3, 2007-FP3-4, 2007FP3-5
Name: M. Nagata and R. Raman*
Affiliation: Himeji Institute of Technology /University of Hyogo and University of Washington*
Spherical torus (STs) has a potential to lead to an
attractive high-beta fusion reactor but in which efficientcurrent drive methods are required for plasma start-up andsteady-state sustainment of discharges because there is noenough space in the center post to install a solenoid coilwith a large amount of flux. Coaxial Helicity Injection(CHI) is one of the most attractive candidates to resolve thenon-inductive current drive and plasma start-up issues forSTs. This approach was initially investigated in Helicity
Injected Torus-II (HIT-II) [1] of University of Washington(UW), National Spherical Torus Experiment (NSTX) [2] ofPrinceton Plasma Physics Laboratory (PPPL) and Helicity
Injected Spherical Torus (HIST) [3] of University of
Hyogo. The UW group with a member of T.R Jarboe, B.A.
Nelson and R. Raman has been leading the CHI researchon NSTX. The CHI experiment on NSTX is in the chargeof R. Raman who takes care of experimental collaborator(M. Nagata) from Japan by the US-Japan personal
exchange program. The main purpose of this collaborative
experiment is to investigate potential of application of the
CHI current drive and start-up method to STs.
The experimental set-up of CHI on NSTX is shownin Fig.1 (a). In the initial experiment, a peak plasma current
up to 390 kA was successfully generated and maintainedfor 300 ms by CHI (injector current 25 kA, voltage 1kV).
DC power supply (50 MW) was used in this experiment.
As shown in Fig. 2, the plasma rotation (20 km/s) driven in
the EB toroidal direction by CHI was clearly identified
by an ion Doppler spectroscopic measurement [4]. The n =Fig. 2. Time evolution of the toroidal current(a), Doppler ion temperature (b) and CIII ion
flow velocity (c).
1 mode was also observed to rotate in the same direction.
This rotating kink behavior observed for the first time in
NSTX is consistent with the electron locking model [1]developed in the HIT-II experiments to explain themechanism of CHI current drive. During the steady-state
CHI operation, MHD relaxation mechanism for current
transfer is required to generate closed flux. Thus, its
identification was one of main research subjects after the
first achievement. Then we had moved on the experiment
for the purpose of plasma start-up. The transient CHI
method for the start-up was proposed in order to produce ahigh quality start-up equilibrium having enough closed flux.
In the initial CHI start-up discharge (capacitor banks:50
mF, 2 kV), we achieved that 3 kA of injector current
produces ~120 kA of plasma current, so the current
multiplication is ~40. Also, results from Fig. 1(b)(c) andequilibrium reconstructions demonstrated the presence of
closed-flux surfaces.
After a significant development of the transient CHI
experiments, the CHI started discharges were successfully
coupled to induction to show compatibility between thetransient CHI and the conventional OH drive. It was shownthat the CHI started plasma current 100 kA ramped up,reaching a peak value of 700 kA (injector current 3 kA) [5].
In this discharge, neutral beams were also injected to heat
the plasma (Te>0.8 keV), triggering an H-mode transition.
These achievements demonstrate the potential for theapplication of this method to future machines.
1) T.R. Jarboe et al., Nucl. Fusion 41 (2001) 679.
2) M. Ono et al., Nucl. Fusion 41 (2001) 1435.
3) M. Nagata et al., Phys. Plasmas 10 (2003) 2932.
4) M. Nagata et al., Plasma and Fusion Research: Rapid
Communications 2 (2007) 0035.
5) R. Raman, et al., Nucl. Fusion 49 (2009) 65006.

Fig. 1. Schematic showing application of CHI in
NSTX (a), fast camera fish-eye image of theplasma during the early phase (b) and later in timeof the CHI start-up discharge (c).

32

Plasma current ramp-up by the vertical field in NSTX
Category: Fusion Physics/ Confinement
Year-Number : 2000-FP2-18,2001-FP2-18,
2002-FP2-15, 2003-FP2-13,2005-FP2-13,
2006-FP2-6, 2008-FP4-3
Name: O. Mitarai, C. Kessel, M. Ono, and M. Peng
Affiliation: Kyushu Tokai University, PPPL and
ORNL
Purpose of collaborative research and its background:
As the spherical tokamak (ST) has no space for thecentral solenoid (CS), it is desirable to start-up the plasma
current without a CS. One of such techniques is the plasma
current ramp-up by the vertical field, which was proposedby author. This technique was already demonstrated in
JT60U, TST-2, and MAST. To confirm this effect and to
apply this technique to the other ST device, NSTX, I(Mitarai) have applied for US-Japan collaborative research
project.

(a)

(d)

(b)

(e)

(f)

(c)



Fig. 2. OH clamp experiments in NSTX. (a) the plasma current,(b) NBI
power, (c) the internal inductance,(d) the surface loop voltage, (e) plasmaenergy, and (f) Ohmic coil current. (#116463 and #116464: NBI with OH
clamp. #116465 No OH clamp.)the efficient heating due to worse high energy particle
confinement. Also experiments were conducted in thelarger internal inductance phase which provides the larger
plasma inductance, leading to the difficulty of the plasma
current increment [1].

Research subjects and obtained results:
 During 2000 and 2006, it was planned to observe theplasma current ramp-up by the additional heating in theconstant ohmic current phase (OH clamp experiment) in
NSTX and then planned to move the heating power to theinitial plasma current start-up phase. From 2008, theplasma current start-up in CTF has been studied, which is acommon subject to above vertical field induction.

2. Study of OH operation in NSTX and the plasma
current ramp-up in CTF
I have obtained very important information on Ohmic
Heating (OH) operation in NSTX, which has never been
seen in the published papers or Laboratory reports. In
NSTX sophisticated operations have been conducted tocontrol of the poloidal field coil current for producing thefield null regime for breakdown. Therefore, I haveconceived the idea to install the cancellation coil (CC) inthe domestic ST, QUEST, for producing the field null for
better plasma breakdown and plasma current start-up
because QUEST has no such sophisticated PF control
system in the initial phase. Actually in QUEST the good
plasma current start-up was obtained using CC at thesecond shot. Thus, the knowledge obtained during the
US-Japan collaboration was very useful for the domestic
experimental program.
I and Dr. M. Peng (ORNL) have been studying theplasma current ramp-up in CTF using the same concept.
Although the plasma current ramp-up to 16 MA by ECRH
and NBI without CS, we are planning to install the small
CS for a reliable plasma current start-up [2].

1. Distinguishable results
Although I have visited NSTX to make experiments forseveral years, remote experiments have been done finallywith Dr. C. Kessel (PPPL) due to machine time schedule.
As shown in Fig.1 in the OH clamp experiment, only one
shot was obtained with plasma current increment by thevertical field and RF heating power, but the other shots did
not show any plasma current increment. In the case ofplasma current of 500 kA, the plasma current was not
additionally increased by NBI heating as shown in Fig. 2.
Those reasons were not cleared yet, but we suspect that the
distance between the plasma and RF antenna was widened,leading to the difficulty of RF injection. On NBI
experiments, the base plasma current might be too low for

3. Summary of my US-Japan collaboration
Although I have gotten slightly negative results in NSTX
experiments, I have efficiently utilized information
obtained during US-Japan collaboration for the domestic
experimental programs. As a result, the plasma current
ramp-up by the vertical field was clearly observed in
QUEST during the constant OH current phase (OH clamp
experiment) differently from NSTX. I can conclude that
my US-Japan collaboration was very successful.
Fig. 1 OH clamp experiments in NSTX. (a) the plasma current,(b)RF power, (c) the internal inductance,(d) the surface loop voltage,(e) plasma energy, and (f) Ohmic coil current. (#115448 and#116449: RF with OH clamp. #116461 No RF with OH clamp.)

1)
2)

33

O.Mitarai, C.Kessel and A. Hirose, JEEE, Vol.129/
No.9/Sec.A (2009) p605
O.Mitarai, Under preparation of resubmission (2010)Collaborations Related Radiofrequency Wave Physics
Category : Fusion Physics/ Steady-State Operation,
Heating and Current Drive
Year-Number : 2000-FP4-8, 2001-FP4-8, 2002-FP4-6,
2003-FP4-3, 2004-FP4-4, 2005-FP2-6, 2006-FP4-4,
2007-FP2-4, 2008-FP2-1, 2009-FP2-4
Name: Y, Takase, M. Ono*, J.R. Wilson*, J.E.
Menard*, R.R. Parker**, P.T. Bonoli**, J.C.
Wright**Affiliation: The University of Tokyo, *PPPL, **MITyears with successive improvements. Plasma initiation wasachieved, but not I p ramp-up. The reason is belieed to be
insufficient RF power delivered to the plasma forming
region.
At MIT, heating and current drive experiments by the
ICRF fast wave and the lower hybrid wave (LHW) arebeing carried out on the high field tokamak Alcator C-Mod,
which is in stark contrast to the ST. Experimental results
are compared directly with the state-of-the-art full wave
analysis codes TORIC and TORIC-LH. Application of
TORIC and TORIC-LH to ST plasmas, which are vastlydifferent from conventional tokamak plasmas, has
contributed to identifications of errors in these codes. These
codes have been improved successively and can now beapplied to HHFW and LHW in ST plasmas. TORIC-LH
has been used to examine scenarios to be used in the planed
I p ramp-up experiments by the LHW on TST-2. TORICLH has the advantage of being able to treat diffraction
effects, which cannot be handled by ray-tracing codes.
Results indicate that low I p , low density plasmas are
suitable targets for lower hybrid current drive (LHCD), but
the propagation region for the LHW becomes restricted tothe plasma edge as I p and density increase. It is therefore
important to keep the density low and to control thewavenumber spectrum. These results provide guidance to I p
ramp-up experiments on TST-2. LHCD experiments havestarted on Alcator C-Mod after a long period of preparation.
This is presently the only LHCD experiment in both Japanand the US. Experimental collaboration on LHCD was
carried out over two years. In 2007, experiments focusing
on parametric decay, which is considered as a candidate
responsible for density limit for LHCD, were conductedsince the usable LH power was limited to less than 0.5 MW.
The experiment could not be performed during the visit due
to a problem with the toroidal field coil, but was carried out
remotely from Japan as a session leader. Even with thefrequency of 4.6 GHz, the upper limit of density for LHW.electron interaction in deuterium plasma was around
1×1020 m-3. This result is an important input to the selectionof frequency for the ITER LHCD system. In 2008, a
continuous density scan was carried out over a wide range,
and it was confirmed that the density limit for LHCD at 4.6
GHz is 1×1020 m-3, and does not depend sensitively oneither the LHW wavenumber spectrum or the magnetic
field strength. An indication of broadening of the LHW
absorption profile was observed when the electron
temperature increased to around 5 keV. In addition, an
experimental proposal to create a current hole and aninternal transport barrier using LHCD during the I p rampup phase was drafted. If successful, this technique may be
used to form an advanced tokamak plasma with highbootstrap current fraction on Alcator C-Mod.

PSFC
A series of collaborations concerning radiofrequency(RF) wave physics on tokamaks [including sphericaltokamaks (ST)] were carried out with groups at Princeton
University Plasma Physics Laboratory (PPPL) and
Massachusetts Institute of Technology Plasma Science andFusion Center (MIT PSFC) as listed below.
FuY 200: Heating experiments by HHFW on NSTX
01: Heating and current drive experiments by HHFW on
NSTX
02: HHFW Current Drive Experiments on NSTX
03: Current Drive and Current Ramp-up Experiments on
NSTX
04: Solenoidless Current Ramp-up Experiments on NSTX
05: Solenoidless Current Ramp-up on NSTX
06: TORIC Simulations of HHFW Heating and Current
Drive in TST-2
07: Lower hybrid current drive and current profile control
experiments
08: Lower hybrid current drive experiments
09: TORIC-LH Simulations of LHCD Scenarios for TST-2
ST has the advantage of being able to confine highbeta plasmas stably. However, this means that the plasma
has a very high dielectric constant. It is believed that thehigh harmonic fast wave (HHFW) could be used effectively
for heating and current drive even in plasmas with very
high dielectric constant. TST-2 at the University of Tokyo
and NSTX at PPPL share the common objective of HHFW
heating and current drive, and started to collaborate on
HHFW experiments on NSTX. Besides obtaining important
experimental results on electron heating, the dependence of
the antenna loading resistance on the neutral pressure wasclarified by analyzing data from HHFW plasma start-up
experiments. In Japan, successful results were achieved inplasma current (I p ) start-up experiments without the use of
the Ohmic heating coil on JT-60U and TST-2. Anexperimental scenario was developed for NSTX and an
experimental proposal was formulated based on theseachievements. Since there were occasions whenexperiments could not be conducted as planned during thevisiting period, due to problems with experimental
hardware or software, arrangements were made to enableremote execution of experiment (not as a mere participant,but as a session leader). Remote execution of experiment
was carried out successfully from the University of Tokyoin 2004. The start-up experiment was carried out over two

3 34
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MR2001-2009 Workshops (Physics of Plasma Merging and Magnetic Reconnection)
Category : Fusion Physics/ Steady-State Operation
Year-Number : 2008-FP2-1, 2009-FP2-2 etc. (20002009)
Name: Yasushi Ono
Affiliation: University of Tokyo

solving the fast reconnection mechanisms an its heating
characteristics and also in exploring fusion applications ofreconnection. Especially, the high power heating of fusion
plasma heating became a economical startup method forSpherical
Tokamaks(STs)
andField-reversed
Configuration (FRCs) for the past 10 years. The mostrecent MR2009 conference was held at Princeton Plasma
Physics Laboratory from March 2 to 4, 2009. The key
subjects were (1) solar satellite “Hinode” observation ofreconnection on solar coronas and chromosphere, (2)theories and experiments for solar flares and micro jets, (3)non-thermal particle acceleration of reconnection, (4)plasma flow and reconnection in laboratory experiments,(5) two-fluid reconnection in magnetosphere and laboratory,(6) current sheet and plasmoid ejections in magnetosphereand laboratory, (7) relativistic magnetic reconnection, (8)trigger mechanism of reconnection and solar flares, (9) 3-D
reconnection research. Presentations from the major four
fields revealed several important common physics: Hall
reconnection, plasmoid and current sheet ejection, nonthermal particle, Hall effect, plasmoid ejection, 3-D
reconnection, anomalous resistivity due to magnetic
fluctuations, relativistic reconnection, promoting theinterrelationship and concrete collaborations amonglaboratory experiments, theories and observations.
Based on contribution of US and Japanesecommunities of magnetic reconnection, a new reconnection
and dynamo COE project: Center for Magnetic SelfOrganization in Laboratory and Astrophysical Plasmas was
accepted by the US National Science Foundation (NSF) in2008 and by Japan Society of the Promotion of Science(JSPS) in 2010, which are now exploring a new stage of
US-Japan collaboration on magnetic reconnection and selforganization caused by reconnection.
1) Ono, Y., Kakuyugokagaku 77 (2001) 948-954.

The purpose of MR Workshops (US-Japan workshop
on Physics of Plasma Merging and Magnetic Reconnection)is to discuss recent progress in physics and applications ofplasma merging/ magnetic reconnection. A series of thisworkshops have been supported by major fourcommunities: laboratory reconnection experiments, solar
observation, magnetosphere observations and theory/
simulations. We had the first MR workshop MR2000 at
University of Tokyo from Feb. 29 to Mar. 4, 2000. About
130 researchers from the four communities discussed thereconnection physics for a week. After MR2000, theMR200X workshops have been held by 50-60 invited andcontributed speakers every year either in US or in Japan
mostly. Figures 1 show photos of laboratory experiments ofmagnetic reconnection: MRX, TS-4, SSX, VTF, UTST,
MST and Caltech Rec. Exp. The series of workshop madeclear that each research field has advantages anddisadvantages. The solar observation can measure a nice 2D image of the sun but a limited local parameters such as
magnetic field and current density because of long distancefrom the satellites to the sun. The magnetosphereobservation can measure all local parameters but not their
special profiles because of a limited number of satellites.
The laboratory experiments is the most powerful tool tomeasure 2-D /3-D profiles of all parameters but theirplasma parameters such as the Lindquest numbers are low
due to their limited special scale. The theory and simulation
can test all kind of physics under the most ideal conditions
but based on some specific assumptions. The collaborationof these four communities made significant progress in

Fig. 1: Laboratory Experiments of Magnetic Reconnection: MRX (Princeton Univ.), TS-4 (Univ. Tokyo), SSX (Swarthmore
College, VTF (MIT), UTST (Univ. Tokyo), MST (Univ. Wisconsin), Reconnection Exp. (Caltech)

3 35
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Two-fluid low-collisionality equilibrium model and application to
rapidly-rotating high-performance spherical tours
Category : Fusion Physics/ High Beta
Year-Number : 2008-FP3-6, 2009-FP3-6
Name: Akio Ishida, L.C. Steinhauer*, Y.-K. M.
Peng**
Affiliation: Niigata University, *Redmond Plasma
Physics Laboratory, University of Washington,**Oak Ridge National Laboratory

Table.

Various computed values

A = 1.4
95 = 2.4
q0 = 1.5
q95 = 10.3
T = 0.1
Ip = 1.2MA
f2F = 1.9

The multi-fluid axisymmetric equilibrium model ofcollisional plasmas was developed earlier [1] where thespecies surface function plays a crucial role.
Yǩ=Ȁ+(mǩ/qǩ)RuǩȀfor Į = i or e
Here \ the poloidal flux and uD\ the species toroidal
velocity. Instead of the adiabatic relation [1], we adopt inthis low-collisionality model the isothermal relation foreach species: TD = TD(YD). This can be deduced from Eqs.
(67), (68) of Ref.[2] assuming the poloidal ion flow is lessthan the ion toroidal flow and taking symmetry of theformalism into account. The system of equations includes
second-order partial differential equations and a Bernoulli
equation for each species. To demonstrate the usefulness ofthe present equilibrium model, we apply it to reconstruct ahigh-performance, long-lived NSTX plasma with high beta
and near sonic rotation [3]. The computational results are
summarized in Table and Figs.1,2. The aspect ratio A,
elongation ǲ , the q-values are in reasonable range of
NSTX [Table]. Fig.1 compares profiles of this example
equilibrium with NSTX shot 113460 (see Fig.2 of Ref. [3]).
Maximum values of temperatures, density and toroidal
velocity are shown in Table. The ratio of the ion toroidal
velocity to the ion thermal velocity at the magnetic axis isnear unity. As a result, the species toroidal current density
is significantly larger than the net toroidal current density[Table]. This extraordinary result differs markedly fromstatic or slowly flowing equilibria. Fig.2 shows the ion fluid
force balance. The ion pressure gradient force (red) is
significantly larger than the Lorentz force (blue) andE+uiuB does not vanish so that two-fluid effects cannot be
neglected. The centrifugal force (purple) is significant near
the magnetic axis. As a result of large two-fluid effect,
species diamagnetic drift rather than the EuB drift is amajor contributor to the cross field drift. This implies that
usefulness of flute-mode suppression by EuB drift shearing
is uncertain in an equilibrium like this. Note that the ion
current is predominantly parallel to the magnetic field. This
follows from the fact that jiIBz (not shown) is significantly
larger than (jiuB)R. One consequence of the large parallel
ion flow near the ion thermal speed is a significant increasein the fraction of passing ions and reduction of trapped ions.
This may affect the standard theories of neoclassical modeland the associated plasma transport (energy, momentum,
particles including impurities) [4].

Te,max = 1.1keV
Ti,max = 1.3keV
nmax = 0.6×1020m-3
uLĳPD[= 249km/s(uLĳ/vth,i)axis = 0.9(jLĳ/jĳ)axis = 2.9(jHĳ/jĳ)axis = 

(a)

(b)

(c)

Fig. 1.Comparison of profiles of the computed equilibriumwith NSTX shot 113460 (see Fig.2 of Ref.3): a) computedion (pink) and electron (cyan) temperatures; b) computed
density (pink); c) computed ion toroidal flow velocity(pink).

centrifugal

(jiB)R















Шpi





enER
5

Fig. 2. Ion fluid force balance: pressure gradient force (red),
Lorentz force (blue), electric force (green) and centrifugal
force (purple).
[1] L.C. Steinhauer, Phys. Plasmas 6, 2734 (1999).
[2] J.J. Ramos, Phys. Plasmas 12, 052102 (2005).
[3] Y-K.M. Peng et al., Plasma Phys. Control. Fusion 47,
B263 (2005).
[4] The present result was submitted to Phys. Rev. Letters,
April, 2010.

36

3.4.4 Diagnostics
The diagnostics area is one of the most active areas in the US-Japan collaboration in the field of theexperimental fusion research. The development of various kinds of innovative diagnostic
instruments has been done. One of them is the development of millimeter wave imaging technology,
aiming at visualizing 2D and 3D structure of plasma. The University of California at Davis (Neville
C. Luhmann, Jr. and Calvin Domier) and Kyushu University (A. Mase and N. Ito) havesuccessfully collaborated on the development of various millimeter-wave devices for advancementof plasma imaging diagnostics. As an example, 1×16 beam shaping and 1×8 beam steering phasedarray antenna (PAA) are fabricated by EF2 technology under the collaboration among UCD,KASTEC, and Kyushu Hitachi Maxell, Ltd. The devices are being applied to microwave imaging
reflectometry (MIR) and electron cyclotron emission imaging (ECEI) systems on DIII-D, LHD,KSTAR and TEXTOR.

NCSX tour during the Microwave Diagnostic(Imaging) Workshop at Princeton in 2005.

Dr. T. Akiyama and Dr. D.L. Brower in front of
the MST Reversed-Field Pinch at Madison.

Neutral particle diagnostics using the silicon surface barrier detector (SD-NPA) started from 1998
under the collaboration of ORNL and NIFS. This program has been proposed from the United Stateside to investigate fast ion distributions in the Large Helical Device (LHD). The specifications of
the method are to observe the low energy particle, to have the lower noise by the liquid nitrogencooling, and to have six horizontal channel and vertical scan system. The dependence of theenergetic particle spectra on the magnetic axis has been investigated. The result obtained is agreed
with the theoretical prediction. N. Nishino at Hiroshima University has been contributing on thedevelopment of two-dimensional ion flow measurement system with Stephen Paul and Robert
Kaita at PPPL. The first attempt to measure the ion flow of NSTX plasma at PPPL was performed.
Development of an advanced impurity transport diagnostic system has been carried out, under thecollaboration between NIFS and the Johns Hopkins University (JHL). The system consists of aTracer-Encapsulated Solid Pellet (TESPEL) developed by NIFS and a spectrometer using a
multi-layer mirror developed by JHL. In this system, a charge exchange spectroscopy can reduce
drastically an ineludible line-of sight integral effect in a spectroscopy. This diagnostic system has
been applied on the LHD and NSTX. US-JAPAN Workshop on “Compact Plasma Neutron Source
for Neutron Assay” was originally inaugurated at Kansai University in 1983 and which has been

3 37
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alternatingly organized in Japan and the United States. The last WS has been held from 12 to 13
October 2009 at University of Wisconsin, Madison, USA. About 55 attendants including 12 fromJapan discussed on the plasma physics and the facility engineering of plasma neutron sources aswell as applications for space propulsion and the production of n-type semi-conductor in addition
to the neutron assay. The measurements and the modeling for numerical analysis have made a large
progress. The new ideas for the improvement of the device such as the magnetized follow cathode,the formation of the cathode by the electron injection and the cylindrical geometry device applying
an axial magnetic filed were discussed.
With advancement of the US-Japan cooperation, the growing amount of experimental data
promoted a Japan-US collaboration to test a freely available TCP acceleration method for fasterthroughput. Typical results showed 90 % of Gigabit Ethernet capability. A series of network
performance tests were made to utilize higher bandwidth on actual 1 Gbps SINET3 and ESnet
connection between MIT (USA) and NIFS (Japan).

NIFS data acquisition group visited the MDSplus
lab of MIT to have a meeting for virtuallaboratory on fusion experiments.

3 38
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A group photo during the U.S.-Japan
Workshop on Millimeter-Wave Plasma
Diagnostics at UCD in 2008.

Development of Advanced Microwave Diagnostic Systems for Magnetic Confinement Plasmas
Category: Fusion Physics/ Steady-State Operation
Year-Number:2004-FP5-18, 2007-FP5-6, 2009-FP5-2
Name: Atsushi Mase, Neville C. Luhmann, Jr.
Affiliation: Art, Science and Technology Center for
Cooperative Research, Kyushu University, Universityof California at Davis (UCD)

antenna, and Yagi-Uda antenna. The comparative study ofthe imaging array has given good performance of thecharacteristics. The system also uses a multichannel IF
circuit after a heterodyne detection. Microwave integrated
circuit power dividers split each of the detector channels
into typically 8 portions, each of which has a filter, detector,
and video amplifier. Therefore, we can obtain the signals at
the poloidal and/or toroidal positions corresponding to thedetector number multiply 8 (radial position). In Fig. 1 isshown a new IF circuit designed at KASTEC where band
pass filters are installed in both sides of a COM line toresolve the IF signal into separate frequency bands. This
type of IF system has been applied to the ECE heterodyne
receiver of KSTAR tokamak, under the Japan-Korea
collaboration program.
The KASTEC and UCD groups have also investigated
the use of new micro-fabrication technologies, electro fineforming (EF2) by Kyushu Hitachi Maxell, Ltd.-Kyushu
University and lithographic galvanoformung abformung(LIGA) by UCD. As an example, quasi-optical notch filterswith rejection frequency in the range of 110-170 GHz andless than 2 dB transmission losses in the pass band are
obtained by EF2, 3) which are better performance than thosefabricated by conventional etching process. The notch filter
is employed to protect the mixer arrays from stray ECRH
power. The filter has been installed in the ECEI systems in
TEXTOR and DIII-D tokamaks operated by UCD-PPPL
and FOM group.
The 2D and 3D profiles of plasma density/temperatureand dynamic behaviors of their fluctuations have beenmeasured by using the above-mentioned imaging systems
in TEXTOR, DIII-D, and LHD. The measurements haveclarified the physics issues such as stability, wave
phenomena, and fluctuation-induced transport.4, 5)
The continuous development of advanced microwave/
millimeter-wave devices is necessary for the improvementof next generation of imaging diagnostics. Those are beamsteering devices, high performance antennas, and highfrequency filters.6)
The recent exchanges from Japan to the US givepriority to the dispatch of young researchers including
graduate students, since the device fabrication andcharacterization have been the main research subjects ofthe exchanges. The period of stay is in the range of 2-3
weeks. A longer stay will be desirable for the collaborative
experiment using the diagnostic system installed in themagnetic confinement devices. Also, the dispatch of young
researchers from the US to Japan will also become
important for the buildup of new cooperation group.

The cooperation program originated in recognition of
the importance of millimeter to submillimeter-wave
diagnostics in magnetically confined plasmas in the early
1980’s. The transmission and scattering processes ofelectromagnetic waves were mainly utilized as diagnostic
tools. As the electron density in magnetically confinedplasmas increased, radar reflectometric process, so calledreflectometry, began to be used in 1990’s since it provides
good spatial resolution and temporal resolution while
requiring a single viewing chord and minimal vacuum
access in contrast to interferometry and Thomson scattering.
Significant advances in microwave and millimeter-wave
technology together with computer technology haveenabled the development of a new generation ofdiagnostics for visualization of 2D and 3D structures ofplasma (mean value of density/temperature and theirfluctuations).1) The main subjects of the exchanges are “thestudy of advanced microwave to millimeter-wave plasma
diagnostic systems and “the application of the diagnostic
systems to large magnetic confinement devices”.
The present cooperation includes execution ofworkshop and personnel exchanges. The obtained results
include fabrication of microwave electronic devices anddevelopment of diagnostic systems using the fabricateddevices. Microwave imaging, for example, electron
cyclotron emission imaging (ECEI) and microwave
imaging reflectometry (MIR), constitute one of thesignificant results.2)
Figure 1 shows the system configuration of the MIR. It
consists of focusing optics, a planar-type array detector,
and a multichannel intermediate frequency (IF) receiver.
The optics can be designed by using a ray tracing code
and/or a 2D finite-difference time-domain (FDTD)
simulation code. The detector consists of the integration ofan antenna array featuring a down-converting mixer using a
Schottky barrier diode bonded to each antenna. Both US
and Japanese groups have developed several types ofantenna elements, such as, bow-tie antenna, dual-dipole
䂾Notch Filter 䋨TEXTOR, LHD䋩
䂾Imaging Array Antenna㩷 䋨LHD, DIII-D䋩䂾Phased Array Antenna䇮Zoom 䋨DIII-D䋩䂾IF Circuit㩷 䋨LHD, KSTAR䋩

1) A. Mase et al., Plasma Device Operations 17 (2009) 98.
2) H. Park et al., Rev. Sci. Instrum. 74 (2003) 4239.
3) Z. Shen, N. Ito, Y. Liang, L. Lin, C. W. Domier, M.
Johnsaon, N. C. Luhmann, Jr., A. Mase, and E. Sakata
Plasma Fusion 2 (2007) S1030.
4) H. Park et al., Phys. Rev. Lett. 96 (2006) 195003.
5) S. Yamaguchi et al., Rev. Sci. Instrum. 79(2008)10F111.
6) Lu. Yang, N. Ito, C. W. Domier, N. C. Luhmann, Jr. and
A. Mase, IEEE Trans. MTT-56 (2008) 767.

Fig. 1. Configuration of microwave imaging system.

3 39
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Development of Microwave Reflectometry
Category : Fusion Physics/ Diagnostics
Year-Number: 2002-FP5-37, 2005-FP5-21, 2006FP5-16
Name: Akira Ejiri, William Peebles,
Shigeyuki Kubota
Affiliation: The University of Tokyo,
University of California, Los Angeles

be measured by reflectometry. The microwave
reflectometer experiments were performed on the NSTX
and the TST-2 devices.
In NSTX, the RF frequency was 30 MHz, and theintermediate frequency of the heterodyne microwave
reflectometer was 28.5 MHz. Therefore, the RF-induced
signals were expected to appear at 30-28.5=1.5 MHz.
Figure 1 (a) shows the power spectrum of the reference
signal around 1.5 MHz. Since the reference signal isindependent of the plasma, the sharp peak at 1.5 MHz
represents the RF-induced noise. A similar sharp peak
appeared in the power spectrum of the plasma signal (Fig.
1(b) red). By analyzing these components, we concluded
that these sharp components arose from the frequency
modulation of the microwave source, which is induced by
the RF at 30 MHz. However, the plasma spectrum shows
addition broad components (Fig. 2(b) blue). The broad
components probably include the RF-induced density
oscillations in the plasma. Thus, we could obtain the upperboundary for the density oscillation from the broad
component. The upper boundary was 0.2 rad, whichcorresponds to the electric field of 20 kV/m.
In TST-2, we used a different type microwave
reflectomter, and noise reduction efforts were made. As aresult, we have succeeded in the direct (phase)measurement of the RF- induced electron density
oscillation and the RF electric field [2].

Various microwave reflectometer experiments werecarried out on the NSTX device, under the collaboration
between the University of Tokyo and the UCLA microwave
diagnostics group. Two types of microwave correlationreflectometers were tested. In addition, RF induced density
oscillation was measured.
Correlation reflectometry is the method to extract
information from the correlation of two or morereflectometer signals. We have tried to extract the pitch
angle of magnetic field lines, and the magnetic fieldstrength.
In general, the parallel correlation length offluctuations is long, while the perpendicular correlation
length is short. Therefore, we can expect that the two
reflectometer signals show a high correlation, when themeasurement positions are connected by the same magnetic
field line. We used three reflectometers in the NSTX device.
Two were located on the same poloidal cross-section, while
the third was separated toroidally by about 20 cm. The
microwave frequency of one of the two reflectometers at
the same poloidal cross-section was swept, while the othertwo frequencies are fixed to different values. By calculating
the correlation between the first two microwave signals, we
obtained the radial correlation function, and confirmed thatthe correlation took the maximum when the two measure
the same position. By calculating the correlation between
the signals from the two toroidally separated reflectometers,
we confirmed that the correlation took the maximum when
the two measured the same flux surface. These results
agreed with our expectation. However, the relationshipbetween the latter correlation and the perpendiculardistance between the magnetic fields are not clear. As aresult, we could not prove the pitch angle measurement.
The O-mode cutoff frequency depends on the density,
while the X-mode cutoff frequency depends on the density
and the magnetic field strength. Therefore, the O-mode andthe X-mode microwave reflectometer frequencies tomeasure the same position are different. By finding thefrequencies, the magnetic fields strength can be obtained asa function of density. The experiments were performed on
the NSTX devices, and we have succeeded in the magnetic
field measurement [1].
Electron heating experiments by High Harmonic Fast
Wave (HHFW) were carried out on the NSTX and theTST-2 spherical tokamak devices. It was shown thatparametric decay instabilities (PDIs) deteriorate theelectron heating efficiency. Since, the PDI is a nonlinear
phenomenon, it is highly desirable to measure the RF
electric field strength in the plasma. Since the RF electricfield induces the electron density oscillation, the fields can

1.5 10-7

1.0 10-7

5.0 10-8

Reference (a)00.0 10-4
4 10Spectral power density[a.u.]

Spectral power density[a.u.]

1) M.Gilmore, W.A.Peebles., S.Kubota, X.V.Nguyen, andA.Ejiri, Rev. Sci. Instrum. 74 (2003) 1467-1472.
2) T. Yamada, A. Ejiri, Y. Shimada, T. Oosako, J.
Tsujimura, and Y. Takase and H. Kasahara, Rev. Sci.
Instrum. 78 (2007) 083502.

-43 10-42 10-4Plasma (b)Signal-4

1 10-4
0

0 100

1.40

1.45
1.50
1.55
Frequency [MHz]1.60

Fig. 1. Power spectrum of the reference signal (a)and that of the plasma signal of the heterodyne
microwave reflectometer, during the HHFW heatingin NSXT.

3 40
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Development of two-dimensional ion flow measurement system
Category : Fusion Physics/ Diagnostics
Year-Number : 2009-FP5-7, 2008-FP5-4, 2007-FP5-7
Name: Nobuhiro Nishino, Stephen F. Paul, Lane
Roquemore, Robert Kaita
Affiliation: Graduate School of Engineering,
Hiroshima University, Princeton Plasma Physics
Laboratory (PPPL)

dimensional ion flow measurement can be performed bythis system.

Transmissivity

1.0This system is the natural extension of a point
measurement SWIFT (shifted wavelength/Interference
Filter Technique)1 system invented by S. Paul to twodimensional measurement. The method for ion flow
derivation by SWIFT is as follows. In Fig.1 the Doppler
shift is determined from the ratio of the light intensity fromtwo detectors. One detector views the plasma through aninterference filter whose pass band has a negative slope,and the other channel views the identical volume of plasma
through a positive-slope filter. The signal ratio varies as theline is shifted across the pass bands. For interference filterswith linear pass bands, that is, constant slopes, the ratio is
not sensitive to ion temperature, and the shifted wavelength
reduces to a simple function of the signal ratio, thechannels’ relative responsibility, and the two filters’transmission curves. Therefore, using two-dimensional
sensor it can be easily extended to two-dimensional
measurement system. It is very attractive to use a fastcamera as a two-dimensional sensor, because the space andtime resolution of ion flow measurement is needed within a
few cm and sub mil-second2, and fast cameras are usedalready as plasma diagnostics. The ultimate target for thetime resolution of this system is within a few tens
microsecond to reveal the flow profile in turbulence.
Figure 2 shows schematic of the proto-type 2-d SWIFT
system installed in NSTX. The system mainly views plasmaedge near the center stack region. Before installing thethroughputs of the optical components were relatively
calibrated, however, we did the double check for theefficiency of two channels without filters using D discharge.
As far as the system views normal plasma, the lightintensity was enough strong to be capable to take a picturewith the speed of several thousand FPS (frame per second).
Then we installed two filters in it and proposed XMP of He
discharge. During He discharge two images near the center
stack were clearly seen. Figure 3 shows two images throughthe negative and positive slope filters, respectively. In Fig.3
red lines are drawn to identify the same position in two
images. The left side of red lines indicates near the middleof the center stack and the light intensity ratio of theseregions was almost constant except during IREs anddisruptions. On the other hand, the right side of red lines
indicates near the inner plasma edge and the line intensity
ratio of these regions changed during normal plasma
discharge even except IREs and disruptions. Thisdifference shows that proto-type SWIFT possibly measured
the ion flow3. Hereafter this system has many points to bemodified, however, in principle we conclude twocollimator
IF

c

BS

a

ԙ


Ԙ

Wavelength ǳ
OutputIrо b@Ԙ㧘 c@ԙ
Ibо b @Ԙ㧘 a@ԙFig. 1.

OutputIr

Doppler shift measurement using two filters

Fig. 2. Proto-type of SWIFT installed in NSTX

Fig. 3. He discharge plasma near center stack
1) Paul, S. F., Rev. Sci. Instrum. 74 (2003) 2098
2) Paul, S. F., et al., Presentation in APS-DPP06
3) Nishino, N., et al., JPFSR 8 (2009) 640

3 41
- 21

OutputIb

Compact Plasma Neutron Source for Neutron Assaycathode wires. The diagnosis confirmed the supposition
that the fusion events occur between the accelerated D ionsand the He3 embedded in the cathode.
Other applications, including neutron assay, wereextensively studied. The IEC fusion device was developed
as a neutron source for land mine detection and showed
good performance. The fundamental experiments to detect
highly enriched uranium (HEU) and explosives werecarried out and exhibited effectiveness. The cylindrical IEC
device was shown to produce a neutron production rate
similar to the spherical device3) and to be useful for neutrontransmutation doping, which is a semiconductor
manufacturing method. The IEC device implanted heliumin W for material testing of the first wall in a fusion reactor.
Since the IEC device is very useful for not only neutron
assay but also various other applications, further efforts toincrease the neutron production will be continued within
the US-Japan collaboration.

Category: Diagnosis
Year-Number: 2009-FP5-1, 2008-FP5-8, 2006-FP5-1
Name: Masami Ohnishi, Gerald Kulcinski
Affiliation: Kansai University, Faculty ofEngineering of Science, University of Wisconsin
A compact plasma neutron source possesses a simple
structure as shown in Fig.1.1) After the vacuum chamber isfilled with a deuterium gas of up to several Pa, then a highvoltage is applied between the cathode and anode. The
glow discharge occurs and the deuterium ions areaccelerated into the mesh cathode. The fusion events
happen between the accelerated ions or the accelerated ionsand the background deuterium molecules. The facility isgiven the name of Inertial Electrostatic Confinement (IEC)fusion.
Figure 2 depicts the neutron production rate achievedin the devices:1) the red bars show the Japanese facilities
and blue ones show the results by US facilities. Almost all
facilities achieved the neutron production 106 to 107 s-1.
The yellow bars display an exceptionally higher neutron
production rate. These facilities were equipped with 6-ionguns.1) The neutron assay application requires a production
rate larger than 109 s-1. In order to increase the production
rate, we have to rely on fusion events between theaccelerated ions. Low pressure operation, ion guns, alarge current discharge with ion sources, and a high voltage
power supply are necessary for achievement of the higher
performance neutron sources.
The IEC device can be operated at low pressure, lessthan 0.01Pa, with the assistance of a magnetron discharge
and showed neutron production rates that scaled in inverse
proportion to the gas pressure, which may be evidence ofthe occurrence of the fusion between the accelerated ions.2)
The similar dependence on the gas pressure can be found in
the devices with the 6 ion guns. The large current dischargeof 5A was demonstrated with RF ion sources in short pulse(6 micro-seconds) in Kansai University.
For these
experiments, the working gas was "normal” hydrogen, thepeak voltage was 70 kV and the gas pressure was 0.2 Pa. A
power supply of voltage 300 kV and current 60 mA wasdeveloped for increasing the neutron production rate byaccelerating the ions to high energy in the University of
Wisconsin devices. This high performance power supply
may enable He3-He3 fusion to occur at rates exceeding
103/s.
It was shown that more than 50% of the D-D fusion
events are caused within the cathode region by the use of atime of flight diagnostic. On the other hand, the D-He3
fusion events were shown to happen mainly within the

Anode

CathodeFig.1 Schematic view of IEC device1)

Fig.2 Neutron production rate of IEC devices1)
1)B.Egle: 11th US-Japan Workshop on Compact Plasma
Neutron Source for Neutron Assay (Madison, 2009).
2) K. Masuda: ibid3) K. Tomiyasu: ibid

42

VUV imaging diagnostics for the study of a tracer-encapsulated solid pellet (TESPEL)
Category : Fusion Physics/ Diagnostics
Year-Number: 2003-FP5-8, 2004-FP5-26, 2006-FP522, 2007-FP5-15
Name: N. Tamura, D. Stutman*, H. Kugel**, S. Sudo
Affiliation: National Institute for Fusion Science,*Johns Hopkins University, **Princeton Plasma
Physics Laboratory (PPPL)

Based on this result, the NIFS group built a soft X-ray
spectrometer with a flat Ru/B 4 C MLM for measuring F IX
(O = 81 Å). The effective excitation rate of F IX for a CX
excited transition is slightly lower than that of Mg XII.
However, in terms of the contribution of CX excitation in
the wavelength of interest, F IX is larger than Mg XII. At
the same time, the JHU group made an imaging
spectrometer with a concave Mo/Si MLM, which has been
provided from the NIFS group, for measuring Li III (O =135 Å). The MLM-based imaging spectrometer allows us
to have the high spatial solution for soft X-ray measurement
easily. The prototype imaging spectrometer was installedon the National Spherical Torus eXperiment (NSTX)
device, in which Dr. D. Stutman has been involved, of the
Princeton Plasma Physics Laboratory for obtaining the test
data. In order to accelerate acquiring the data from theimaging spectrometer in the tracer impurity measurement,
the TESPEL injection into a NSTX plasma was performed.
As shown in Fig. 2(a), the TESPEL was successfully
injected into the NSTX plasma by using a lithium pellet
injector, which is already installed on NSTX. Figure 2(b)shows the temporal evolution of a signal from the imaging
spectrometer in the case that a lithium tracer was
introduced. As a reference, the signal in the case that any
tracer impurity was not introduced into the NSTX plasma isalso shown in Fig. 2(b). As can be seen from Fig. 2(b), theMLM-based imaging spectrometer successfully captured
the signal from the tracer impurity ions introduced into the
NSTX plasma [3]. These achievements enable us to
improve the performance of the advanced impurity
transport diagnostic system.

In the Large Helical Device (LHD) of the National
Institute for Fusion Science (NIFS), we are establishing an
advanced impurity transport diagnostic system by means ofa Tracer-Encapsulated Solid Pellet (TESPEL). In thissystem, a Charge eXchange Spectroscopy (CXS), which
can reduce drastically an ineludible line-of-sight integral
effect in a spectroscopic measurement, is a key element.
The past study has revealed that the CXS with a negativeion-based NBI, the acceleration voltage in which is so high(~180 keV), for measuring the spatio-temporal behavior oftracer impurity ions introduced into the LHD plasma by the
TESPEL should be performed in the VUV and soft X-ray
domain. Thus this research subject is aimed to develop the
spectroscopic system with a high spatial resolution, a highsensitivity and a high efficiency for the light in the VUVand soft X-ray range. A multi-layer mirror (MLM) has ahigh reflectivity for the light in the VUV and soft X-ray
range. So the development of the system has been done incollaboration with the Johns Hopkins University (JHU)
plasma spectroscopy group (main collaborator: Dr. Dan
Stutman), which has a significant background in the
spectroscopy by using the MLM. As a first step, in order toassess the capability of the MLM-based spectrometer forthe tracer impurity measurement, a proto-type soft X-ray
spectrometer with a flat Ni/C MLM for measuring Mg XII(O = 45.5 Å), which was built by the JHU group, wasinstalled on LHD. A typical result from the experiment with
the TESPEL containing a magnesium tracer is shown in Fig.
1. As can be seen from Fig. 1, the signal from themagnesium tracer impurity ions was successfully obtainedwith a high S/N ratio by the prototype spectrometer [1, 2].

1) D. Kalinina et al., J. Plasma Fusion Res. 80 (2004) 545.
2) D. Stutman et al., Rev. Sci. Instrum. 76 (2005) 013508.
3) D. Stutman et al., Rev. Sci. Instrum. 77 (2006) 10F330.

TESPEL injection timeTESPEL injection time

Photons on MCP(x106 s-1)
TESPEL injection time

Fig. 2. (a) Image in Li I light of LiH-filled TESPEL,
injected in low density NSTX L mode. (b) Telescope
traces following injection of empty and LiH-filled
TESPELs in low density L mode. A current amplifier
6
Fig.
Image
Li Inolightof LiH-filled
TESPEL,with2.10(a)V/Againinanddiodebias was usedin thisinjected
in low density
NSTX
measurement.[fromRef.
3] L mode. (b) Telescope
traces following injection of empty and LiH-filled
1) TESPELs
D. Kalininainetlow
al.,density
J. Plasma
FusionARes.
80 (2004)
545.
L mode.
current
amplifier2) withD. Stutmanal., Rev.
Sci.diode
Instrum.
106 V/Aetgain
and nobias 76
was(2005)
used in013508.
thisRef.Sci.
3] Instrum. 77 (2006) 10F330.
3) measurement.[fromD. Stutman et al., Rev.

Fig. 1. Background subtracted 45.5 Å signal (+) andMIST simulation assuming 7 x 1017 Mg atoms
injected at r /a < 0.7 and 1.5 m2/s constant diffusivity[from Ref. 2].

3 43
- 23

Data Access Optimization for “Virtual Laboratory” on Fusion Experiments
Category : Fusion Physics/ Diagnostics
Year-Number : 2008-FP5-7, 2009-FP5-13
Name: Nakanishi Hideya, Joshua A. Stillerman
Affiliation: National Institute for Fusion Science,
Massachusetts Institute of Technology (MIT)Experimental or observational devices of the socalled big sciences in the world have a common tendency togradually become bigger in size and fewer in number. This
increases the need for their data to be shared over highperformance wide-area networks.
TCP/IP is de facto standard Internet technology andis integral to remote data sharing platforms. However, it has
a well-known long fat-pipe network (LFN) problem thatcauses drastic speed lowering in long-distancecommunications [1]. This lessens the effective throughput
even though physical layers have much wider bandwidths.
It is a significant obstacle to wide-area data transfers andremote data sharing in general for fusion and other big
science research projects.
To further scientific collaboration, some virtualprivate networks have been constructed on the Japanese
academic information highway SINET3. One of them isdedicated for fusion research and named SNET. The LFN
problem is also serious on the 1 Gbps SNET; for example,
standard Windows or Linux PCs can use only 40 Mbps
between NIFS and Kyushu Univ. whose distance is 1000km with about 20 ms round-trip time (RTT) on network.
More distant Japan-US communications with 200 ms RTT,
the effective throughput is down to only few Mbps.
A TCP/IP WAN commercial accelerator, Fujitsu
Wan Director A100, was applied on the top of someprimary SNET sites. It provides 300 Mbps throughput
between NIFS and Kyushu Univ. stably, however, its
embedded encryption prevents it from reaching the 1 Gbps
physical bandwidth. The cost is prohibitive for mostacademic uses [1].
The growing amounts of experimental data
prompted a Japan-US collaboration to test a freely
available TCP acceleration method for faster throughput.
Typical claimed results were 90% of Gigabit Ethernet. A
series of network performance tests were made to utilize
higher bandwidth on an actual 1 Gbps SINET3 and ESnet
connection between MIT (USA) and NIFS (Japan) [2].
With the combination of tuned TCP parameters andthe packet pacing by inserting pause packets, the observed
throughput did reach 90 % of the 1 Gbps ideal bandwidth(Fig. 1). Its effective throughput was 750 Mbps that is 2.5
times higher than WDA100. Note that the necessary
software is completely free.
This successful achievement using 90 % of fullbandwidth has proved the technical possibility to share theenlarged experimental data internationally. Its advanced
technology together with coming 10 Gbps networks will beessential for the next-generation projects like ITER.
Additional improvement by using the guaranteed quality of
network service (QoS) is also planned.

Fig. 1. LFN test results between NIFS and MIT
A different approach to above mentioned data
throughput acceleration, is to use a compressed transport torun remote user interfaces for applications that operate on
computers close to the data. Extensive tests looking at dataof Alcator C-Mod were performed from Japan (Fig. 2).
As remote data access performance is dominated by
the transaction costs, reducing the number of transactions
required for data access improved the remote data display
significantly. However, running a compressed X Window
server NX [3] and running the application close to the data
was significantly better still.
Continuous data growth causes that 80% of thewhole data is less than 3 years old. We also concluded that
this detracts from the usefulness of most caching schemes.

Fig. 2. Possible methods for distant data access: Using
MDSplus client/server, US-JA tests were done on(i)~(iii) methods.
1) Nakamura, M., et al., Proc. ISPAN (2004) 294.
2) Nakanishi, H., et al., Proc. 7th IAEA TM on Control,
Data Acquisition, and Remote Participation for Fusion
Research, Aix en Provence, France, 15-19 June 2009.
3) http://www.nomachine.com/

3 44
- 24

Neutral Particle diagnostics using the silicon diode array
Category : Fusion Physics/Diagnostics
Year-Number : 2004-FP5-19, 2003-FP5-1
Name:Tetsuo Ozaki, Jim Lyon
Affiliation: National Institute for Fusion Science
Oak Ridge National Laboratory

means that the pitch angle scattering becomes large in thehigh-Z plasma. The high ion temperature can be obtained
because the mechanism induces the input of the energy tothe ion. SD-NPA provides the spectrum differences
between the low and high-Z plasmas.

Neutral particle diagnostics using the silicon surface
barrier detector (SD-NPA) starts from 1998. The neutral
particle spatial distribution can be easily obtained. The
project has been proposed from the United State side inorder to install it on LHD and to investigate the mechanismof the energetic particle in the helical plasma. The
specifications of the method are to observe the low energy
particle, to have the lower noise by the liquid nitrogencooling and to have six horizontal channel and vertical scansystem in order to see the particle on the whole twodimensional area. The meaningful time window is 100 ms1).
Figure 1 is the schematic drawings of the main part andthe movable stage. In the LHD, all equipments arecontrolled remotely because nobody can enter the LHD hallduring discharge. The experimental data are acquired
automatically. Figures 2 and 3 show the vertical andhorizontal sight lines from the SD-NPA on the LHD. The
pitch angle and the equivalent radius are varied by the small
different sight angle because the LHD has a complicatedmagnetic configuration. The pitch angle is defined as anangle between the magnetic line and particle direction.
Figures 4 (right and left) show the pitch angel and theequivalent radius.
Figure 5 shows the difference of the energetic particle
spectra when the magnetic axis is varied. In the helicaldevice, the cross section of magnetic surface is different
from that of the particle orbit surface. In the standard
magnetic configuration, the cross section of the particle
orbit surface is shifted inner than that of the magnetic
surface. The cross section of the particle orbit surface isdetermined by the device. However the cross section ofmagnetic surface can be changed by the variety of thevertical magnetic strength. When the magnetic axis is
moved inner, the particle confinement can be improved
although the plasma stability becomes worse theoreticallybecause the cross section of the magnetic surface is close to
the particle orbit surface. When the particle emits to theoutside of the plasma, the particle is lost due to the charge
exchange between the background neutral and the particle.
In Figure 5, much particle remain in the plasma when themagnetic axis is shifted inner. The result obtained from thedetector is agreed with the theoretical prediction.
In the LHD, the high-Z gas is used in order to obtain
the high plasma parameters, especially the high ion
temperature. By this way, the high ion temperature can beobtained because the ion density is relatively small and the
input power can be concentrated to the ion. In theexperiments, the neon and the argon gases are used insteadof the hydrogen gas. In the high-Z plasma, much particle
flux can be obtained even at the high-energy range. This

Fig. 1 (left upper) the main part and the movable stage,
Fig. 2 (left lower) the vertical sight lines,
Fig. 3 (right upper) the horizontal sight lines,
Fig. 4 (right lower) (left) the pitch angle,(right) the equivalent radius.

Fig. 5 The spectra at the different magnetic axis.
1) P.R. Goncharov, J.F. Lyon, T. Ozaki, S. Sudo, et al.
JPFRS, 5 (2001), pp. 159 - 162.

45

3.4.5 High Energy Density Science
The Japan-US collaborations on the high energy density science have played important rolls in theinertial confinement fusion and the high density plasma physics of both countries in the last decade.
The subjects covered in the collaborations are 1) Fast ignition laser fusion theory and simulation,2) Impact Ignition laser fusion, 3) Fabrication, injection, and tracking of fast ignition targets, 4)
Heavy ion inertial confinement fusion, 5) Plasma devices for probing warm dense matter, 6) Fast
ignition experiments, and 7) Laser laboratory astro-physics. Several workshops and personal
exchanges have been organized to initiate collaboration works and to start joint experiments andsimulations.
In the theory and simulation for fast ignition, the principal investigators are K.Mima andH.Nagatomo (ILE, Osaka University) for Japan and Y.Sentoku (University Nevada, Reno),
G.Shvets (University Texas, Austin), R.Sephens (GA), and C.S.Liu (University Maryland, CollagePark). 4 workshops and one joint workshop with the experimental group were held. The highlightsof the workshops are the developments of integrated code and code validation by experiments. The
Osaka University, NIFS and Setsunan University developed the integrated code, FI3, whichconnects three different codes, namely, PIC, Fokker Planck code, and radiation hydro codes. On
the other hand, University Nevada, GA, and LLNL developed a hybrid code named LSP and alarge scale PIC with collision, named PICKLS. Based upon those codes, relativistic electron
generation and transport, and the resulting heating process of imploded plasmas were investigated.
In collaboration with fast ignition experimental group lead by K.Tanaka (Osaka University) andR.Stephens (GA), the relativistic electron energy spectrum, transport, hydrodynamics andintegrated performance of fast ignition cone target were investigated. One of the highlights of theexperimental group is the joint experiment at ILE, Osaka University with GXII and Peta watt lasers
and at LLE, University Rochester with OMEGA-EP laser on the heating processed, hydrodynamics
diagnostics and integrated performance of cone targets.
As a new ignition scheme, the impact ignition was also studied jointly with NRL group. The
principal investigators are H.Azechi and M.Murakami of ILE, Osaka University and Steve
Obenshain (NRL). This group collaborated on the high velocity acceleration of a foil andintegrated impact heating experiment, theory and simulation. The highlights of this activity are thedemonstration of the acceleration of foil up to 1000km/sec and 100 timed enhancement of neutron
yield by the impact. Those experiments were carried out with NIKE Kr laser and GXII laser. The
result of the neutron enhancement was published in Physical Review Letters.
In the target fabrication, injection, and tracking, the principal investigators are T.Norimatsu (ILE,
Osaka University) and D.Goodin (GA). Two workshops in the US and one workshop in Japan were
held. The objectives of this field were fabrication of fast ignition target and related R&D of low
density foam and injection and tracking of a reactor size target. The foam cryogenic target has beendeveloped by the collaboration among GA, NIFS, and ILE, Osaka University. The R&D toward thehigher quality target is continuing.
As for the heavy ion beam inertial fusion, The 4 workshops and 3 personal exchanges have beenorganized by S.Kawata (Utsunomiya University), M.Ogawa (Tokyo Institute of Technology),
G.Logan (Lawrence Berkley National Lab.), and R.Davidson (Princeton University). The Japanese
research group collaborated with the US Virtual National Laboratory for Heavy Ion Fusion formany years on the HIF target design, HIB driver technology, and physics of beam transport andinjection. A new target design for mitigating RT instability has been proposed.

46

Finally, the collaboration on the basic high energy density physics was organized by R.Kodama(Osaka University), M.Ozaki (Osaka University), R.Smith and M.Key (LLNL). The highlights ofthis collaboration are “Development of plasma device related to laser proton acceleration” and“ Proton probing for laser-driven dynamically compressed matter”. The further collaborations inthis field are expected by using large laser facilities in US (NIF) and in Japan (LFEX).

47

Workshop on Theory and Simulation of Fast Ignition Laser Fusion
Category: High Energy Density Science
FY and Number: 2003-FP5-25, 2004-FP5-30, 2005JF1-3, 2007-FP5-8
Principal Investigator: Kunioki Mima, Hideo
Nagatomo
Affiliation: Institute of Laser Engineering, Osaka
University

improve the both simulation code. In the discussion, hotelectron spectrum is one of the most important issue in thefast ignition research.
Radiation
Hydro SM.
Particle SM.
 Density, temperature, charge stateThe goal of the workshops is to realize an integrated
simulation code for fast ignition laser fusion. In the four
workshops, the following 4 topics are discussed. The one is
the numerical modeling of plasma physics related to fast
ignition. The second is code validation by comparing theresults with experimental results. The third is theintegration methodology of a few different simulation codes.
The final subject is application of integrated code totarget design and the analysis of experimental data.
 Two workshops were held in US, and two workshops
were in Japan. In those workshops, LLNL (A.Kemp,
R.Town, S.Wilks, S.Hatchett, M.Key, B.Langdon) GA and
Univ. Nevada (Y.Sentoku), GA (R.Stephen), LANL
( R.Mason), UCLA (W.Mori), Ut.Texas, Austin (G.Shvets,
T.Ditmyer),PPPL(NatFisch), Un. Meryland (CS Liu), Univ.
Rochester (J.Myatt, C.Ren) participated from USA.
From Japan, Osaka University (K.Mima, H.Nagatomo,
H.Shiraga, T.Johzaki, K. Tanaka, H.Shiraga, H.Azechi, andR.Kodama), NIFS (H.Sakagami), Setunan University(T.Taguchi), Kyushu University (Y.Nakao), and so on
participated.
AS the related subjects, the workshop shed light on therelativistic laser plasma physics related to fast ignition andother applications of ultra-intense laser. The workshop
consists of overview the present status of relativistic laser
plasma physics and some special topics. In particular, themethodology for comprehensive simulation of relativistic
laser plasmas has been investigated. The fast ignition
integrated interconnected code ( FI3) has been developed at
ILE, Osaka University, which includes 4 simulation codes ;PIC, PIC-fluid hybrid , Fokker Planck, and Radiation
Hydro. The highlights of the discussions were onelectromagnetic turbulence generated by relativistic
electron beam, radiation recoil effects on the extremely
high intensity laser plasma interactions, the high energy ion
generation, and so on. The dynamics of the Weibel
instability and the following electromagnetic turbulence arefound to play important rolls in the cone shell target fast
ignition. The more theory and simulation discussions will
be continued further in the following workshop. The joint
workshop for the validation of simulation codes, was heldat Ootsu city in Japan, in 2007.
Two examples of achievement in the workshops aredescribed in the following. The Japanese group proposed
the integrated simulation code called FI3. The structure ofthis integrated simulation code is shown in the Fig.1. The
FI3 can describe the over all processes included in the fast
ignition. On the other hand, the US group developed LSP
as a fast ignition integrated code. In the workshop, theresults of these two simulation codes are compared toHighenergyelectrondeposition
profile High energy
Electrondistribution
Fokker Planck SM.

Fig. 1. FI3 (Fast Ignition Integraed Interconnecting Code)Fig.
1. FI3 (FastIntegraed
Interconnecting
Radiation
HydroIgnition
simulation,
particlesimulationCode)and
Radiation
Hydro
simulation,
particle simulation andFokker-Planck
simulation
are interconnected
Fokker-Planck simulation are interconnected

(1)

(2)

Fig.2 (1) time dependent density profile of plasmas
interacting with pico second heating pulse, (2) electronenergy spectrum for long scale (a) and short scale cases
1) H. Sakagami, et al., Laser Part. Beams 22, 41(2004); 24,
191 (2006).
2) A.Kemp, Y.Sentku, etal, PRL 101(2008)075004

48

Basic and integrated studies for fast ignition
diameter with 7-Pm-thick wall and its material is CD(deuterated plastic). A typical laser intensity pattern isshown in Fig.1 simulated with PIC simulation. The goldcone appears to increase the laser intensity.
Nine laser beams of the GEKKO irradiate a CD shell for
implosion with 1.2 ns pulse at a 532 nm wavelength widthof a flat top shape at an energy of 2.5 kJ. Random phase
plates are inserted in all the beams. Implosions are also
simulated with a one-dimensional fluid code. The
implosion timing is monitored with an x-ray streak camera
and agrees well with the simulation. At around the
maximum compression, the PW laser of 300 J in 0.6 ps isinjected into the Au cone tip. According to our simulation,
the Au cone tip survives to the maximum compression. The
imploded core is created at about 50 Pm away from the tip,which gives a very good coupling of hot electrons to thecore. The compression process is also monitored with an xray framing camera making use of the x-ray backlight of Pt
at 2 keV, which could give an estimation of the core density.
The diameter and the density of the core are 30–50 Pm and
50–100 g/cm3, respectively. The density is reduced fromfitting the back lighting data with a simulation. The PW
injection is confirmed as a clear x-ray signal with the x-ray
streak camera.
Neutrons of 104 are observed just from implosion
without the PW heating. When the ultra-intense laser pulses
at 0.5 PW are injected into the cones at max compression,
the neutron yield increased to almost 107. In the previous
study of fast heating at a 100 TW laser power, a similar
compressed core was created and was estimated to have a
300 eV plasma temperature. In this experiment thetemperature rise from 300 to 800 eV is also consistent withthe 1000 times neutron increase.

Category : High Energy Density Science
Year-Number : 2002-FP5-13,
Name: Kazuo A. Tanaka, Richard Stephens
Affiliation: Osaka University, General Atomics
The fast ignition scheme of inertial fusion energy
consists of various aspects of relativistic laser matterinteractions as well as the feasibility study of the scheme
itself by making use of integral type experiments. We haveconducted the basic and integrated studies for FI. The basic
study includes details of hot electron production with anultra-intense laser pulse. The integrated includes a model FI
experiment, which shows an enforced heating of a core witha PW (Peta watt) ultra-intense laser pulse. The
collaboration has been achieved with Richard Stephens etal. at General Atomics and Max Tabak et al. at Lawrence
Livermore National Laboratory, U.S.A.

FIG. 1. The E field is shown of an ultra-intense laser pulse incident into a
54° cone perpendicular to the polarization in the three-dimensional
particle in cell (PIC) simulation. The concentration of the E field along
the cone axis is clearly shown. 20 times increase is indicated over theoriginal intensity 4x1018 W/cm2. The scale of X and Y directions arenormalized by the laser wavelength 1 Pm. The figure is at t=100 fs, while
the ultra-intense laser pulse is 20 fs. The simulation is calculated in
14x9x9 Pm box.

A PW laser system has been constructed in the samelaser bay of the GEKKO 12 laser beam system at theInstitute of Laser Engineering, Osaka University. The PW
system has a 50 cm beam diameter and can deliver up to
500 J on-target within 0.5 ps at 1053 nm with a 5 nm
bandwidth. The GEKKO laser system has 12 green beams
whose oscillator takes a part of the PW front-end light. The
synchronization is within 10 ps between the PW and
GEKKO pulses because both systems use the same originof light. The GEKKO laser system delivers 2.5 kJ at 532
nm onto a target with random phase plates with a 1.2 ns
quasi-square pulse shape. The two laser systems were used
to conduct a FI model experiment where the PW laser pulse
is injected through a Au cone to heat a compressed core
imploded by the GEKKO laser beams.
A Au cone inserted on a plastic shell is imploded and isheated to model enforced heating of an imploded highdensity core using both GEKKO and PW laser systems. The
gold cone has a 30° opening angle with a 5 Pm tip
thickness at 50 Pm diameter. The shell is 500 Pm in

FIG.2. Neutron number vs fast heating laser power. The triangles show
the data without fast heating. The squares show the data with fast heating.
The neutron increase is 1000 times with the heating compared to the ones
without it. The fitted curves are the ones with 30% and 15% coupling
efficiencies from the ultra-intense laser to the core heated energy.

KA Tanaka et al., PHYSICS OF PLASMAS 10, 1925
(2003)
2. R Kodama et al., Nature, 412, 7989, (2001); R Kodama
et al., ibid. 418, 933 (2002).
1.

49

Japan-US Workshop on Progresses of Impact Ignition
collides with the main fuel with a density of 400 g/cm3.
Here, the implosion and acceleration processes are
neglected. The impactor in a bullet-shape initially has
spatial extensions of 60 and 70 m in the perpendicular andthe parallel directions with respect to the collision axis,
respectively. The main fuel has a concave shape to tamp
the impactor, as is observed in an implosion with a cone.
The impactor energy is only about Ei ~ 10 kJ, whereas themain fuel has a much higher energy than this. However, if
the energy of the main fuel is reduced so that it is one to
two times the impactor energy, i.e., Em ~ 10-20 kJ, and if atypical coupling efficiency of Kc ~ 10 % from the laser tothe internal energy of the fuel assembly is assumed, we
estimate that the laser energy for ignition will be EL =(Ei+Em)/Kc ~ 200-300 kJ. This energy is much lower thanthat required for central hot spot ignition and is comparable
to that required for conventional fast ignition. The primarychallenges are thus to generate such high velocities while
maintaining target integrity and to achieve such highimpactor densities. Throughout this study, unless statedotherwise, we define the time origin as the time of
maximum compression of the main fuel.

Category: High Energy Density Physics
Year-Number: 2009-FP6-3
Name: M.Murakami, H.Nagatomo, T.Johzaki,
Y.Arikawa, T.Watari, Steve Obenscain
Affiliation: Institute of Laser Engineering, Osaka
University, Naval Research Laboratory
In impact ignition scheme [1], a portion of the fuel(the impactor) is accelerated to a super-high velocity,
compressed by convergence, and collided with aprecompressed main fuel. This collision generates shockwaves in both the impactor and the main fuel. Since thedensity of the impactor is generally much lower than thatof the main fuel, the pressure balance ensures that theshock-heated temperature of the impactor is significantly
higher than that of the main fuel. Hence, the impactor Here
we report major new results on recent impact ignition
research: (1) A maximum velocity ~ 1000 km/s has beenachieved under the operation of NIKE KrF laser at Naval
Research Laboratory (laser wavelength = 0.25Pm) in theuse of a planar target made of plastic and (2) We have
performed two-dimensional simulation for burn andignition to show the feasibility of the impact ignition.
Impact ignition, as well as the other designs such as hotelectron-driven fast ignition [2] and shock ignition, reduces
driver energy requirement by heating a portion of DT fuelin terms of an additional heating mechanism. The
significant advantage for these approach is to separate thecompression from the heating. This report describes
experiments that, for the rst time, reach target velocities
in the range of 700 – 1000 km/s. The highly accelerated
planar foils of deuterated polystyrene, some with bromine
doping, are made to collide with a witness foil to produce
extreme shock pressures and result in heating of matter tothermonuclear temperatures. Target acceleration andcollision are diagnosed using large eld of viewmonochromatic x-ray imaging with backlighting as well as
bremsstrahlung self-emission. The impact conditions are
diagnosed using DD fusion neutron yield, with over 106
neutrons produced during the collision. Time-of-ight
neutron detectors are used to measure the ion temperature
upon impact, which reaches 2 – 3 keV. The experiments
are performed on the Nike facility, recongured
specically for high intensity operation. The shortwavelength and high illumination uniformity of Nike KrF
laser uniquely enable access to this new parameter regime.
Intensities of (0.4  1.2) x 1015 W/cm2 and pulse durationsof 0.4  2 ns were utilized. Modeling of the target
acceleration, collision, and neutron production is
preformedusing
thetwo-dimensionalradiationhydrodynamics code with a non-LTE radiation model.
Moreover, detailed analytical model addresses thefeasibility of even higher velocities. (see Fig.1)
Our hydrodynamic simulation shown in Fig. 2
demonstrates [3] that ignition occurs when an impactor
with a velocity of 1750 km/s and a density of 50 g/cm3

Fig. 1. X-ray image of impact collision (left) andtemporal evolution of the velocity

Fig. 2. Snapshots of density and temperature
distributions obtained from the two-dimensional
simulation. At t = 110 ps, ignition and burn can beobserved with temperatures > 30 keV.
1) Murakami, M. and Nagatomo, H., Nucl. Inst. & Meth.
Phys. Res. A544 (2005) 67.
2) Azechi. H., et al., Nucl. Fusion 49 (2009) 104024.
3) Azechi, H., et al., Phys. Rev. Lett. 102 (2009)235002.

50

Plasma Devices for Probing Laser-Driven High Pressure Condensed Matter
Category: High Energy Density Science
Year-Number: 2006-FP5-26, 2007-FP6-17,
Name: R. Kodama and N. Ozaki, Raymond Smith,Mike KEY
Affiliation: Graduate School of Engineering, Osaka
University, Lawrence Livermore National Laboratory

Proton probing for laser-driven dynamically compressed
matter㩷 㩷 㩷 㩷 㩷 Motivated by the IFE research, the development ofpulsed power facilitie has allowed the emergence of a new
field, High Energy Density laboratory Physics.[3] Amongthe techniques commonly used for generation of HED
matter states, shock compression has been very successful
either on the principal Hugoniot or on off-Hugoniot states.
However current standard visible diagnostics cannot accessparameters as important as density. In crucial contexts, thisuncertainty prevents reaching the high precision required todiscriminate between theoretical models. Moreover, thedevelopment of new high energy laser facilities, such as
NIF or LMJ, will allow us to study very high pressures,over 10 TPa, where the validity of optical diagnostics muststill be verified. This is the reason why significant efforts
have recently been carried on in order to develop new
diagnostics able to penetrate compressed matter, permitting
the investigation of its microscopic properties. A novel
approach employs energetic protons as radiographic sourcefor density characterization of warm dense plasmas.
Protons have a greater ability to penetrate thick materials,
giving a higher signal to noise ratio and they can provide
views from multiple angles.
Nano-second pulse laser beams were used tolaunch a shock wave into a main target and hence create awarm dense shocked state. The shock was then transmitted
into a sliver of low-density carbon foam. The proton beam
was generated in the interaction of a pico-second pulse
laser beam with a gold foil. The detector was placed at a
distance from the main target on the transverse axis, givinga projection magnification of > 10. The detector consisted
on a film pack containing radiochromic dosimetry films.
Each film accounts for a different proton energy in therange 3.5-15 MeV. Protons of different energies have a
different time of flight from the source to the shock target
and so changes occurring on time scales corresponding to
the variation in TOF can be detected. The possibility to use
this technique as in situ diagnostic of warm dense states
was for the first time demonstrated. High quality
radiography of shock compressed targets have beenobtained (Fig. 2).

Plasma Device developments; Relativistic plasma
shutter for intense proton generation
The development of ultrashort, high-power lasers has
produced record pulse intensities up to 1022 W/cm2.[1]However, as the peak intensity increases the required
contrast ratio between: (i) a temporal pedestal caused by the
ASE; (ii) prepulses, caused by the residual aberrations of
the spectral phase, and the main pulse needs to be
proportionally improved to allow for pre-plasma freeinteraction with solid targets. The use of high contrast,
prepulse free pulses for interaction of ultrahigh intensity
lasers with solids is of primary importance for a number ofhigh field experiments such as high harmonic generationand proton acceleration. Specifically, experimental data andparticle-in-cell simulations suggest the maximum protonenergy increases, in some cases, dramatically, as the target
thickness is reduced for sufficiently high laser intensity andcontrast.[2]A relativistic, transmissive plasma shutter (Fig. 1) wastested in order to improve the sub-100 ps contrast of a highintensity laser pulse and allow a clean interaction withultrathin targets. The relativistic plasma shutter was a thin
foil placed in front of the main target so that the leadingedge of the laser pulse fully ionizes the foil. In order for theplasma shutter to be effective, the ablated foil must expand
such that the peak electron density n e is greater than thenonrelativistic critical density and less than the relativistic
critical density. This plasma will transmit the high-intensity
peak pulse while rejecting the low intensity pedestal
resulting in an increase in temporal contrast. Here, theimproved contrast was confirmed by measuring high-energy
protons at three different angles from the target rear withand without a plasma shutter inserted. The result was the
production of 1.8 MeV protons from a shuttered 30 nm
target, while no protons were detected for a 30 nm
standalone target. The relativistic plasma shutter technique
is simple to implement and scalable as the laser power isincreased.
Fig. 1: Schematicof the relativistic
plasma shutter for
ultra intense laser
pulses.

Fig. 2: Whole RCF set for asnapshot taken 7ns after themain ns pulse beams.

1) S. W. Bahk et al., Opt. Lett. 29, 2837 (2004).
2) S. S. Bulanov et al., Med. Phys. 35, 1770 (2008).
3) Frontiers in high energy density physics, N.R.Concil,
The National Academy Press (2003).

3 51
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Fabrication, Injection and Tracking of Fast Ignition Targets
Category : High Energy Density Science
Year-Number : 2001-FP5-37, 2004-FP5-8,
Name: Takayoshi Norimatsu, D. Goodin*
Affiliation: Institute of Laser Engineering, Osaka
University, * General Atomics, USAIn both the cone target and cone-less target approaches tofast ignition target design, fusion fuel must be compressed“cold” (along a low isentrope curve) to a high density
exceeding >1000 times solid density before the compressedfuel core is heated to >10 keV with a fast ignitor beam.
The techniques being demonstrated for fabrication andhandling of direct drive targets will be directly applicable tocone-less fast ignition targets.
The OMEGA Cryogenic Target Handling System(CTHS) provides cryogenic targets for direct-drive
implosion experiments on the OMEGA laser at the
University of Rochester Laboratory for Laser Energetics.
The OMEGA direct drive targets are 0.9 mm in diameterwith a 3-Pm-thick outer plastic ablator and an inner ice
layer that ranges from 80 to 100 Pm thick.
The inner-ice-surface nonuniformities are characterizedusing a shadowgraphic technique as shown in Fig. 2. The
parallel rays from a light source are refracted at the plastic
shell and reflected by total internal reflection from the inner
ice surface, thus forming a virtual bright ring. The brightring in the recorded image is unrolled using the center ofthe shadow of the plastic shell as a reference point,providing a graph with the distance of the inner ice surface
from the center of the shell as a function of angle. The
difference in the measured distance of the ice surface froma perfect circle is then decomposed into cosine modes,
resulting in a nonuniformity spectrum of the inner ice
surface. These measurements provide a 2-D representationof the inner-ice-surface nonuniformity along one circular
cut through the sphere. It is possible to fully map a 3-D
nonuniformity spectrum by rotating the target and acquiring
2-D power spectra for different slices through the ice.

The Japan-US workshops on Fabrication, injection,and tracking of fast ignition target were held at General
Atomics USA in 2001, ILE, Osaka university in 2004 andGA in 2007, respectively. Followings are highlights from2001 and 2004 workshops, which were reported elsewhere[1].
Fabrication of low-density foam and drilling of fragile
foam shell are current issues in the fabrication of fast
ignition target with reentrant cone. Fuel loading to thetargets is a challenging issue in the mass-production
process of the targets for a fusion power plant. Two fuelloading methods are proposed for the fast ignition target
with the cone. Preliminary experiments of injection andtracking of real size targets have started showing promising
results.
An important approach is to control the fuel shape by
wicking it into a supporting foam structure. Conceptually
the separation of layer shape from the ambient isotherms
allows considerable freedom in target design. Practically,
there are still difficulties. First among them attaining afoam density that won’t invalidate the experiments.
Calculations (see Fig. 1(a)) show that in a full scale reactor
a target using 30 mg/cc foam could have some gain, andwould have excellent performance when its density is
below ~10mg/cc. Such a foam shell is not feasible yet,but neither is ignition our initial goal. Foam method is theprimary candidate to produce the hollow solid DT layer in
the FI target with the cone. Basic elemental technologies
to make both targets already exist. Future reactor size
targets might be fabricated by improving existing
technologies but demonstration is necessary using actual
material and size. The thermal cavitation technique or
feeder pipe method (Fig. 1(b)) can be applied for a futuremass-production process of the FI target with cone.

(a)Fig. 2 Quality of solid Dr layer for corn-less fast ignition
target at Rochester University[1] T. Norimatsu et al., Fusion Sci. Technol., 49 p483
(2006)(b)

Fig. 1 The gain curve of fast ignition target with foam (a)and the way of fuel loading by a tube (b).

3 52
- 32

Robust fusion energy release from a fuel pellet in heavy-ion inertial confinement fusion
Category: High Energy Density Science
Year-Number: 2000-FP5-1, 2001-FP5-19, 2004-FP517, 2005-FP5-1, 2006-FP5-10, 2007-FP6-3, 2008FP6-1
Name: *S. Kawata, *1M. Ogawa, *1K. Horioka, *1Y.
Oguri, *2M. Murakami, *3K. Takayama, *4H.
Yoneda, *5G. Logan, *5J. Barnard, *5, *6R. Davidson
Affiliation: *Utsunomiya Univ., *1Tokyo Inst.
Tech., *2Osaka Univ., *3KEK, *4Tokyo University ofElectro Communications, *5HIF-VNL, Lawrence
Berkeley National Lab., *6Princeton University

An example result shows 84% reduction of the R-T
instability growth (see Fig. 3).Fig. 1. The relationship between a beam emittanceand the divergence angle. The HIB illumination isprecisely computed.

In our collaborations with collaborators in the U.S.
Virtual National Lab. for Heavy Ion Fusion, we havestudied for many years on heavy-ion-beam (HIB)
accelerators, HIB propagation, HIB-target interaction and
HIF fuel target implosion study, including new approaches
to warm dense matter physics (WDMP), Rayleigh-Taylor
instability growth control, etc.[1-3] HIB has unique features
for inertial fusion: 1) A precise control of HIB, including
HIB pulse shape, particle energy, HIB axis control, ion
species, etc. 2) HIB energy deposition is well defined
precisely by a well-known physics inside matter. The HIB
energy is deposited inside matter, and this feature can beutilized for WDMP. The HIB energy deposition area israther wide and thick inside a matter. 3) HIB generationenergy efficiency is rather high, that is, about 30~40% fromelectricity to HIB energy.
Nonuniformity of HIB illumination is one of key
issues in the HIB inertial confinement fusion (ICF):
implosion symmetry should be less than a few percent inorder to compress a fuel sufficiently and release fusionenergy effectively. In this collaboration a new HIB
illumination scheme (see Fig. 1) was persued in order torealize a robust illumination scheme against a displacementof a direct-driven fuel pellet in an ICF reactor. It is known
that the HIB illumination nonuniformity is sensitive to alittle pellet displacement from a reactor chamber center; apellet displacement of only 50–100 Pm [1] was tolerable inthe conventional beam illumination schemes. In this workby three-dimensional computer simulations a new robust
HIB illumination scheme was found, in which a 200–
300 Pm displacement is allowed as shown in Fig. 2.
A new mitigation method of the Rayleigh-Taylor(R-T) instability growth was also studied in order to make a
HIF target robust against a non-uniform implosion. In thisstudy a new mitigation method of the R-T instability growthis proposed based on an oscillating perturbed acceleration,
which can be realized by a rotating or oscillating HIB
illumination onto a fuel pellet. The R-T instability analyses
and fluid simulations demonstrate that the oscillating
acceleration reduces the R-T instability growth significantly.
In this paper a baseline steady acceleration g 0 is
perturbed by a perturbed oscillating acceleration Gg , whichis spatially non-uniform and oscillates in time ( g 0 !! Gg ).

Fig. 2. The rms nonuniformity versus the pellet
displacement dz in a reactor chamber for the beam
radius of 3.4 mm and 4.6 mm, a pellet of the Al layer
structure, the external pellet radius of 4.0 mm and the
32 HIBs system. 'T = 2 degree.

Fig. 3 The Rayleigh-Taylor (R-T) instability control
example results under the oscillating acceleration. The
R-T instability growth is controlled and reduced
significantly by the oscillating acceleration
perturbation, induced by the HIB axis wobbling.
1) T. Someya et al., Phys. Rev. ST-AB 7 (2004) 044701.
2) S. Kawata et al., Nucl. Instrum. Methods Phys. Res.,
Sect. A, 606 (2009) 152.
3) K. Horioka et al., Nucl. Instrum. Methods Phys. Res.,
Sect. A, 606 (2009) 1.

3 53
- 33

54

CHAPTER 4

Joint Institute for Fusion Theory (JIFT)

4.1 Objectives
The distinctive objectives of the JIFT program are (1) to advance the theoretical understanding ofplasmas, with special emphasis on stability, equilibrium, heating, and transport in magnetic fusion
systems; and (2) to develop fundamental theoretical and computational tools and concepts forunderstanding nonlinear plasma phenomena. These objectives are pursued through collaborations
between U.S. and Japanese scientists by means of two types of exchange program activities —
namely, workshops and exchange visitors.

4.2 Activities
Each year the JIFT program usually consists of four topical workshops (two in each country) andsix exchange scientists (three from each country). So far, during its 28 years of successful
operation, JIFT has sponsored 166 long-term visits by exchange scientists and 102 topical
workshops.
• The workshops typically have an attendance of 15–30 participants, of whom usually three
to seven scientists (depending on the particular workshop) travel to the workshop from thenon-host country. Scientists from countries other than the U.S. and Japan are also often
invited to participate in JIFT workshops, either as observers or multi-laterals.
• Of the approximately three exchange visitors in each direction every year, one—called the“JIFT Visiting Professor”—is supported by the host country, while the others—called“Exchange Scientists”—are supported by the sending country. The visits of the Exchange
Scientists usually last from several weeks to two or three months in duration, whereas the
Visiting Professors normally stay for the period of three months.

Participants at the JIFT Workshop on Advanced Simulation Methods in
Plasmas (December 2009, National Institute for Fusion Science).

55

The topics and also the participating scientists for the JIFT exchange visits and workshops are
selected so as to have a balanced representation of critical issues in magnetic fusion research,
including both fundamental problems as well as questions of near-term significance, and also totake into account the specific capabilities and interests of both countries. The Japanese and US
members of the JIFT Steering Committee agree together on the appropriateness of proposed
topics before recommending them.

Participants at the JIFT Workshop on Theory and Simulation on Ultra-Intense
Laser Plasmas (November 2008, University of Texas at Austin).

The category of JIFT exchange activities called Joint Computational Projects program wasinstituted in 1985 to take advantage of the dedicated data link between the MFE Computer
Center at LLNL (now called NERSC and located at LBNL) and the computer center of theInstitute of Plasma Physics in Nagoya. In the early days of the US-Japan fusion collaboration,
this JIFT data link was about the only of its kind, allowing data sets to be transferred back andforth and even allowing remote usage of computational facilities in one country by physicists inthe other. However, the regular Internet now provides a sufficiently fast communication tool forscientists who wish to access their institution's computers remotely and exchange data throughlow- and medium-bandwidth lines. After discussions between the US and Japanese JIFT partners,
it was decided at the annual meeting of the JIFT Steering Committee held at Dallas (Nov. 19,
2008) to terminate the Joint Computational Projects category of JIFT exchange activities at theend of Japanese Fiscal Year 2008 in accordance with the expiration of the Annex II document on
a Data Link and Data link projects for fusion. The JIFT Steering Committee wrote a 30-page
report about the history and achievements of the Data Link and the Joint Computational Projects(http://peaches.ph.utexas.edu/ifs/jift/references.html).
Information about the JIFT program, including annual schedules of exchange activities, can befound on the US JIFT web site at http://peaches.ph.utexas.edu/ifs/jift/ on the US side. A
corresponding Japanese JIFT web site at http://www-nsrp.nifs.ac.jp/JIFT/ was set up in 2008,56

with information such as previous JIFT annual reports and JIFT meetings in Japan.

4.3 Administration
JIFT has a Steering Committee consisting of eight members, four from each country. Two ofthese members are the Japanese and US co-chairmen. Two other members of the Steering
Committee, the US and Japanese co-executive secretaries, are responsible for the ongoing daily
oversight of the progress of JIFT activities. The co-chairman and co-executive secretary on the
US side are, respectively, the director and associate director of the Institute for Fusion Studies(IFS) of The University of Texas at Austin. The Japanese co-chairman is the executive directorof the Numerical Simulation Research Project at the National Institute for Fusion Science, andthe Japanese co-executive secretary is the director of the Fusion Theory and Simulation Research
Division in the Department of Helical Plasma Research at the National Institute for Fusion
Science. Furthermore, on the Japanese side there is an Advisory Committee comprised of several
members representing a spectrum of Japanese universities and the Japan Atomic Energy Agency;
and on the US side there is an Advisory Committee comprised of several members representinga spectrum of US universities and national laboratories.
The JIFT Steering Committee attempts to schedule workshops in such a way as to dovetail withother meetings. It also encourages participation at workshops by interested experimentalists andinvites relevant available scientists from other countries to attend workshops.
As the principal program for fundamental theoretical exchanges in the US-Japan Fusion
Research Collaboration, JIFT operates alongside the Fusion Physics Planning Committee(FPPC) and the Fusion Technology Planning Committee (FTPC). In particular, the JIFT
activities are coordinated with the four FPPC areas of activity, viz., core plasma phenomena,edge behavior and control, heating and current drive, and new approaches and diagnostics.

Participants at the JIFT Steering Committee Meeting (November 2004)

57

4.4Accomplishments and Highlights
A number of general benefits have resulted over the years from the JIFT program. In particular, thefollowing may be cited: JIFT has provided efficient communication channels for the latest
theoretical research results, techniques, and directions; JIFT activities have attracted serious
participation from allied fields such as fluid turbulence, statistical physics, computational science,and space plasma physics, which brings new scientific tools into the fusion program and enhances
the stature of fusion physics; JIFT exchanges have contributed to efficient utilization ofinternational research facilities; and, JIFT emphasis on large-scale computational studies hasreaped significant mutual benefits from the supercomputer resources and code-building expertiseof both countries.
Through JIFT, close and long-lasting scientific connections have been established between the U.S.
and Japanese fusion theory communities. Not only have senior scientists profited from thesecollaborations, but also young scientists—and even, on occasion, advanced graduate students—
have had many opportunities to enhance their research careers. Some of highlights of achievements
are shown hereafter.
JIFT activities have led to the publication of numerous scientific papers, as well as review articles
and books. JIFT research has also been featured in a number of invited talks at major international
meetings (e.g., the biennial IAEA Fusion Energy Conference.) A list of JIFT-related publications is
attached.

58

Simulationof Alfvén
Alfvén eigenmodes
eigenmodes
Simulation Studies
Studies ofCategory : Joint Institute for Fusion Theory
Year-Number : 2000-JF1-9, 2004-JF1-12, 2006-JF1-4
Name: Y. Todo, D. A. Spong*, H. L. Berk**, B. N.
Breizman**Affiliation: National Institute for Fusion Science (NIFS),

excited by the MHD nonlinearity after the TAE modesaturation.
D. A. Spong studied Alfvén eigenmodes in several
stellarator conﬁgurations including LHD during his visit to
NIFS in the year 2007. The shear Alfvén spectrum in threedimensional conﬁgurations, such as stellarators and rippled
tokamaks, is more densely populated due to the larger
number of mode couplings caused by the variation in themagnetic ﬁeld in the toroidal dimension. A new algorithm
based on the Jacobi–Davidson method was developed andapplied for a reduced MHD model3). This techniquefocuses on ﬁnding a subset of eigenmodes clustered about aspeciﬁed input frequency. A three-dimensional structure
for a TAE mode in LHD is shown in Fig. 2.

*Oak Ridge National Laboratory (ORNL), **Institute for
Fusion Studies, University of Texas at Austin (IFS)
Toroidal Alfvén eigenmode (TAE) bursts and nonlinear
MHD effects on the TAE evolution were studied while Y.
Todo visited IFS in the years 2000 and 2005. The TAE
bursts are phenomena where multiple TAE’s arerecurrently destabilized by the neutral beam injection. The
behaviors of the multiple TAE’s are synchronized and thefast ion losses take place associated with the TAE
destabilization. The TAE bursts are observed in many
toroidal magnetic confinement devices. The first numericaldemonstration of TAE bursts was performed withparameters similar to a TFTR experiment and many of theexperimental characteristics were reproduced1). These
include: (a) the synchronization of multiple TAE’s taking
place at time intervals fairly close to the experimental
value; (b) the modulation depth of the drop in the stored
beam energy that closely matches the experimental value;(c) the stored beam energy saturating at about one-half to
one-third of that predicted for a classical slowing down
distribution. Figure 1 shows the time evolution of thedominant two modes (2 and 5) and the density of the coinjected beam ions. To understand the beam ion loss
mechanism, we studied surface of section plots where only
one eigenmode is taken into account and the amplitude ofthe eigenmode is at a constant value. It was found particle
loss is due to: (1) the resonance overlap of different
eigenmodes; (2) the disappearance of KAM surfaces inphase space due to overlap of multiple nonlinear islands
created by a single eigenmode. The synchronization of themultiple TAE’s takes place due to the resonance overlap.
However, the saturation amplitude was B/B~10-2 which
is higher by one order of magnitude than the value inferredfrom the experimental plasma displacement measurements.
Then, we investigated the nonlinear MHD effects
comparing two types of simulations. In the standard
simulation, the full nonlinear dynamics of both the MHD
fluid and the energetic particles is simulated. In the otherversion of the simulation, only linear MHD equations areused while the nonlinear particle dynamics is retained. In
the results of the two codes2), no significant difference wasfound for low saturation levels, B/B~10-3. In contrast,
when the TAE saturation level predicted by the linear codeis B/B~10-2, the saturation amplitude in the fully nonlinear
simulation was reduced by a factor of 2 due to thegeneration of zonal (n=0) and higher-n modes. This
reduction is attributed to the increased dissipation arisingfrom the non-linearly generated modes. The fully nonlinear
simulations also show that geodesic acoustic mode is

4.0 100
0.02

3.5 100
3.0 1000

r/a=0.22

r/a=0.39

2.0 100

B/B

mode 5

2.5 100

nb [a.u.]

0.01

mode 2-0.01
r/a=0.55
r/a=0.72

1.5 100-0.02
r/a=0.89

1.0 100-0.03

r/a=1.05
5.0 10-1

0.0 10r/a=1.22-0.04

r/a=1.39

0

61

62

63

64

65

66

t [ms]

Fig.1. Time evolution of the dominant two modes and theco-injected beam ion density at various minor radius1).

Fig.2. Three-dimensional eigenmode structure for aTAE
mode in LHD3).
1) Y. Todo, H. L. Berk, and B. N. Breizman, Phys. Plasmas
10, 2888 (2003).
2) Y. Todo, H. L. Berk, and B. N. Breizman, to appear in
Nucl. Fusion 50 (2010).
3) D. A. Spong, E. D’Azevedo, and Y. Todo, Phys.
Plasmas 17, 022106 (2010).

59

Gyrokinetic simulation of drift wave turbulence in magnetically-confined plasmas
Category : Fusion Physics/ Theory
Year-Number : 2002-JF1-10, 2008-JF1-12
Name: T.-H. Watanabe, *)W. Horton
Affiliation:
National
InstituteforFusionScience, *)Institute for Fusion Studies, University ofTexas at Austin (USA)is found that a coherent vortex structure (right) with a lowtransport level is spontaneously formed after the ETG
turbulence (left).
The present research collaboration has recently been
extended for the ETG turbulence and zonal flows in atokamak and a linear magnetic confinement device.

The present research collaboration started since Dr.
Watanabe stayed at Institute for Fusion Studies (IFS),
University of Texas at Austin, in November 2002 as avisiting researcher supported by the US JIFT program.
Then, the collaboration studies have been continued invarious ways. In 2008, Prof. W. Horton (IFS) visited
National Institute for Fusion Science (NIFS), and stayed
three months. During this opportunity, we could effectively
conduct research collaborations on simulation of drift wave
turbulence in magnetized plasmas. Here, we report two
major results obtained under the JIFT program.
i) Research collaborations using GKV code
Gyrokinetic simulation code, GKV, which solves the
gyrokinetic equation as a nonlinear partial differential
equation in the five-dimensional phase space, has beendeveloped at NIFS, with the aim of analyzing the drift wave
turbulence in magnetically-confined toroidal plasmas. Bymeans of GKV code, we have intensively investigated theion temperature gradient (ITG) driven turbulent transportand zonal flows in a tokamak and the Large Helical Device(LHD).
Since numerical simulations dealing with the fivedimensional phase space demand huge amount of computerresources, their successes largely rely on realization ofefficient computing on massively-parallel supercomputers.
We revised GKV and MEGA codes (the latter is developedby Prof. Todo at NIFS for analysis of high-energy particle
confinement) so as to be executed on Franklin at NERSC
and Ranger at University of Texas, and compared theirperformances with those of supercomputers available atJapanese sites [1]. The both codes newly installed inFranklin and Ranger show good scalability over 10,000
processor cores (see Fig.1).

Fig. 1. Computational performance of GKV code on
severalmassively-parallel
supercomputers.
Horizontal axis is normalized by the computation
speed measured by using the NEC SX-7/160M5
system (after Ref. [1]).

ii) Simulation of electron temperature gradient turbulence
The electron temperature gradient (ETG) turbulence
has been considered as one of possible causes for the
anomalous electron heat transport in magnetized plasmas.
Prof. Horton and his collaborators have investigated the
ETG turbulence by means of the two-dimensional fluid
simulations. In Japan, Mr. Nakata, the Graduate Universityof Advanced Studies (Sokendai), has carried out
gyrokinetic simulations of the slab ETG turbulence.
Utilizing the opportunity of the Prof. Horton’s stay at NIFS,
we conducted the research collaborations on the ETG
turbulent transport [2].
Color contours for fluctuations of the electrostatic
potential and the electron temperature are shown in Fig.2. It

Fig. 2. Potential [(a) and (b)] and temperature [(c) and(d)] fluctuations found in the slab ETG mode
simulation during turbulent [(a) and (c)] and quiescent[(b) and (d)] phases (after Ref. [2]).
1) T.-H. Watanabe, Y. Todo, and W. Horotn, Plasma
Fusion Res. 3, (2008) 061.
2) M. Nakata, T.-H. Watanabe, H. Sugama, and W.
Horton, Phys. Plasmas 17, 042306 (2010).

60

JIFT Workshops on Theoretical Analyses in Helical Plasmas
Category: JIFT
Year/Number: 2004-JF1-01
Names: D. Monticello (PPPL), N. Nakajima (NIFS)
Dr. Monticello and Dr. Nakajima organized a series of
two workshops on theoretical physics issues in 3D toroidal
magnetic confinement systems.
1. First workshop (Princeton, 2002)
A workshop entitled “Theoretical Consideration on
Helical Plasmas” organized by Dr. Nakajima (NIFS) and
Dr. Monticello (PPPL) was held in Princeton on November
18-21, 2002. Sixteen talks were presented. The talks
focused mostly on stellarator experiments that wereoperating at the time of the conference (LHD, Heliotron-J,
W7-AS, and HSX) and on proposed experiments such as
QPS, W7-X, and NCSX. A synopsis of all the talks was
prepared by Nakajima and Monticello and published in the
May 2003 edition of Stellarator News [1]. The talks wereposted on the workshop website [2]. Several results fromthis workshop are shown in Figs. 1-3 here.

Fig. 2. NCSX divertor model with field line traces [fromtalk by A. Grossman et al.)]

2. Second workshop (Kyoto, 2005)
A follow-on workshop, entitled “Progress oftheoretical analyses in three dimensional configurations,”
with the same two organizers, was held in Kyoto on
January 25-27, 2005. There were five participants from the
US and seventeen from Japan. The US representatives were
A. Boozer (Columbia), C. Hegna (Wisconsin), L.
Sugiyama (MIT), A. Ware (Montana), and D. Monticello(PPPL). The talks covered a wide range of stellarator
physics, including equilibrium, MHD stability, kinetic
stability, pellet ablation, and edge physics. Probably mostinteresting were the details of theoretical analyses of theexperiments on the Large Helical Device (NIFS) thatattained plasma beta of 4.2%. A report on the workshop,with a synopsis by the US participants, was presented to
the US stellarator physics community on February 10, 2005,
as part of the National Stellarator Theory seminar series.
The talks were posted on the workshop website [3]. This
information was also announced in Stellarator News.

Fig. 3. Local Island Divertor (LID) using m/n = 1/1[from talk by R. Kanno][1] http://www.ornl.gov/sci/fed/stelnews.
[2] http://www.pppl.gov/ncsx/Scientificconf/JIFT/JIFT.html[3] http://www.center.iae.kyotou.ac.jp/kondok/meetings/jift/presentations.html
Fig. 1. Pellet deformed by non-uniform heat flux [from atalk by R. Ishizaki, R. Nakajima, and P. B. Parks)]

61

Micro-Instability Analysis of Toroidal Confinement Devices

Large Helical Device,” Nuclear Fusion 42, 1047-1054(2002).

Category: JIFT
Year/Number: 2004-JF1-04
Names: G. Rewoldt (PPPL), H. Shirai (JAEA), N.
Nakajima (NIFS)(a)Dr. Rewoldt has been involved in three general areasof work for the Joint Institute for Fusion Theory program.
He made many trips to Japan under its auspices. These
areas of research were:(1) Ideal MHD equilibrium and stability analysis ofstellarator/heliotron devices, in particular Heliotron-E,
using the STEP code, a modified version of the PEST code,
which implements the so-called stellarator expansion. This
work was done in collaboration with J.L. Johnson (PPPL),
M. Wakatani and Y. Nakamura (Kyoto University Plasma
Physics Laboratory), and others, over the period from 1985
to 1991.
(2) Linear and quasi-linear gyro-kinetic microinstability analysis of the JT-60U tokamak using the FULL
code, in collaboration with K.W. Hill, W.M. Tang, andothers (PPPL) and H. Shirai, Y. Kishimoto, and manyothers (JAERI). This work involved calculations of linear
growth rates and real frequencies and ratios of quasi-linear
fluxes, using realistic experimental density and temperature
profiles and MHD equilibria, over the period from 1999 to2005.
(3) Linear gyrokinetic micro-instability analysis of the
LHD stellarator using the FULL code, in collaboration with
L.-P. Ku and W.M. Tang (PPPL), W.A. Cooper (CRPPEPFL), and H. Sugama, N. Nakajima, K.Y. Watanabe, S.
Murakami, H. Yamada, and many others (NIFS), over theperiod from 2000 to 2003. In these calculations, modes
such as trapped-electron modes and ion temperature
gradient modes can be unstable, with contributions fromboth toroidal curvature and helical curvature to resonancesof both toroidally trapped and helically trapped electrons.
Numerous publications resulted from these joint
collaborations. Selected papers are listed below [1-5].

(b)Fig. 1. Quasilinear particle flux * and energy flux
Q as functions of the electron temperature gradientparameter, compared to experimental values. [fromRef. 3][1] R. Nazikian, K. Shinohara, G.J. Kramer, E. Valeo, K.
Hill, T.S. Hahm, G. Rewoldt, S. Ide, Y. Koide, Y.
Oyama, H. Shirai, W. Tang, “Measurement of
Turbulence Decorrelation during Transport Barrier
Formation in a High Temperature Fusion Plasma,”
Phys. Rev. Lett. 94, 135002 (2005).
[2] H. Takenaga, S. Higashijima, N. Oyama, L.G. Bruskin,
Y. Koide, S. Ide, H. Shirai, Y. Sakamoto, T. Suzuki,
K.W. Hill, G. Rewoldt, G.J. Kramer, R. Nazikian, T.
Takizuka, T. Fujita, A. Sakasai, Y. Kamada, H. Kubo,
and JT-60 Team, “Relationship between particle andheat transport in JT-60U plasmas with internaltransport barrier,” Nuclear Fusion 43, 1235-1245(2003).
[3] G. Rewoldt, L.-P. Ku, W. M. Tang, H. Sugama, N.
Nakajima, K. Y. Watanabe, S. Murakami, H. Yamada,and W. A. Cooper, “Microinstability Studies for the[4] G. Rewoldt, L.-P. Ku, W.M. Tang, H. Sugama, N.
Nakajima, K. Y. Watanabe, S. Murakami, and H.
Yamada, “Drift Mode Calculations for the Large
Helical Device,” Phys. Plasmas 7, 4942-4947 (2000).
[5] Y. Sakamoto, T. Suzuki, S. Ide, Y. Koide, H.
Takenaga, Y. Kamada, T. Fujita, T. Fukuda, T.
Takizuka, H. Shirai, N. Oyama, Y. Miura, K.W. Hill,
G. Rewoldt, and JT-60 Team. “Properties of Internal
Transport Barrier Formation in JT-60U,” presented at
19th IAEA Fusion Energy Conference 2002; Nucl.
Fusion 44, 876-882 (2004).

62Effect of Resistive Wall on External Kink Modes

Category: JIFT
Year/Number: 2004-JF1-06
Names: M.S. Chu (GA), K. Ichiguchi (NIFS)
Dr. Chu from General Atomics spent three months at
NIFS as the JIFT Visiting Professor (September 1–
November 31, 2004). During this time, he performed
research in collaboration with Dr. K. Ichiguchi concerning
the possibility of resistive wall modes in 3D magnetic
confinement configurations.
The external kink mode is one of the most serious
instabilities that affect plasma confinement. Its growth rateis usually fast, outside the range of feasibility for plasma
control. The external kink mode can be stabilized by thepresence of a nearby perfect conducting wall. When theresistivity of the wall is taken into account, the externalkink mode is changed into the resistive wall mode (RWM).
Its growth rate then reduces to the inverse of the flux
diffusion time through the resistive wall. The RWM with
its slower growth rate can be stabilized either by plasma
rotation or magnetic feedback. In configurations without
toroidal symmetry, plasma rotation is relatively small andnot expected to stabilize the RWM. Therefore, magnetic
feedback must be relied upon to stabilize the RWM in nonaxisymmetric configurations. As preparation for the designfor feedback control of the RWM, the growth rate of the
RWM in these configurations was investigated.
A method was formulated for the systematiccomputation of the growth rate of the RWM in weakly
unstable 3D configurations by using results from ideal
stability codes. It was shown that the growth rate of the
RWM is given, approximately, by the rate at which theavailable free energy for the ideal external kink mode (withthe wall at infinity) can be dissipated by the resistive wall.
By relying on the concepts of energy and dissipation, themethod is readily connected with other MHD codes andprovides an independent and useful method of studying thephysics of RWM.
This formulation was demonstrated by coupling to theideal MHD code KSTEP to study the stability of the RWM
in LHD plasmas. It is found that in terms of plasma current,a very limited range of the plasma equilibria can have its
external kink mode affected by the presence of the resistive
wall, i.e., the plasma quickly transits from being stable withrespect to the external kink mode to being unstable evenwhen the wall is upon on the plasma. Nevertheless, it wasdemonstrated that the proposed method can be used toevaluate the growth rate of the RWM in any 3D
configurations readily. The growth rate in the advanced
stellarators can also be calculated by employing full 3D
codes such as CAS3D and TERPSICHORE instead of the
KSTEP code.

Fig. 1. Radial profile of the plasma displacement of theunstable ideal kink mode across the flux surfaces.

Fig. 2. Computed growth of the Resistive Wall Mode
(RWM) as a function of the wall position [from Ref. 1].

[1] M. S. Chu and K. Ichiguchi, “Effect of the resistive
wall on the growth rate of weakly unstable externalkink mode in general 3D configuration,” Nucl. Fusion
45, 804 (2005).

63

Particle acceleration and parallel electric field in collisionless shock waves
Category : JIFT
Year-Number : 2004-JF1-14, 2009- JF-3,
Name: Y. Ohsawa, W. Mori*, J. Van Dam**,W. Horton**
Affiliation: Nagoya University, *UCLA, **IFS

magnetic field. If E|| =0, therefore, this type of acceleration
cannot take place either. The effect of E|| on relativistic ionsbecomes small as the particle energy goes up; thus, thetheoretical treatment ignoring E|| [6] is justified.

With the JIFT personnel exchange program, I visited
The University of California at Los Angeles (UCLA) andInstitute for Fusion Studies (IFS), The University of Texas
at Austin, in 2004 and the IFS in 2009. With plasma
physicists at these institutions I discussed particle
acceleration, nonlinear wave structure, and simulation
methods. I was happy that I was able to collaborate withoutstanding American plasma physicists, such as W. Mori,
J. Leboeuf, V. Decyk, W. Horton, C. Chiu, J. Van Dam,and H. Berk. In particular, the electric field parallel to themagnetic field, E || , in nonlinear magnetosonic waves was
one of the main topics we worked on together [1].
In the ideal MHD, the parallel electric field E || is zero,and it was generally thought that E || is quite weak in lowfrequency phenomena in high-temperature plasmas. We
have found out, however, that it can be strong inmagnetosonic shock waves [2,3]. Our theory and relativistic,
electromagnetic, particle simulations show that themagnitude of the parallel pseudo potential F, which is theintegral of E || along the magnetic field B, in a smallamplitude (H<<1) magnetosonic wave is eF~H* e T e in a highbeta plasma, where * e is the specific heat ratio of electrons,
and is eF~Hm i v A 2 in a low beta plasma. For largeamplitude waves with Ha2 1) (shock waves), it iseF~H m i v A 2+ * e T e ), which is valid for both high and low
beta cases. Figure 1 compares the theory and simulation
results for the case of shock waves [2]. Furthermore, thiswork has been extended to electron-positron-ion (e-p-i)
plasmas; positrons act to decrease the magnitude of F, andin a pure electron-positron plasma it becomes zero [3]. This
explains the simulation result that the positron acceleration
along the magnetic field in e-p-i plasmas becomes weak as
the positron density decreases [4].
The parallel electric field plays an essential role in
the acceleration of electrons [5] and of positrons [4] inshock waves, while it was ignored in the theory of theincessant acceleration of relativistic ions [6]. Having
obtained the above quantitative theory for E || , we haverevisited the effect of E || on these acceleration mechanisms
with use of particle simulations and two types of test
particle calculations: In one method we have used the total
electric field in the relativistic equation of motion for test
particles, while in the other method we have used theelectric field perpendicular to B.
This study [1] indicates that without E||, electron
reflection near the end of the main pulse of a shock wave,
which triggers electron acceleration and trapping, does notoccur, and thus the acceleration mechanism reported in Ref.
[5] does not operate (see Fig. 2). The positron accelerationin an e-p-i plasma discussed in Ref. [4] is nearly along the㩷Fig. 1 Parallel pseudo potential F versus shock amplitude.
The closed circles and triangles show F while the open ones
represent electric potential formed in shock waves [2].

㩷Fig. 2 Phase spaces (x, J) of test electrons. The upper andlower panels, respectively, show test electrons calculatedwith total and perpendicular electric fields. There are many
ultrarelativistic (J>100) electrons in the upper panel [1].
1) S. Takahashi, H. Kawai, Y. Ohsawa, S. Usami, C. Chiu,
and W. Horton, Phys. Plasmas 16, 112308 (2009).
2) S. Takahashi and Y. Ohsawa, Phys. Plasmas 14, 112305(2007).
3) S. Takahashi, M. Sato, and Y. Ohsawa, Phys. Plasmas 15,
082309 (2008).
4) H. Hasegawa and Y. Ohsawa, Phys. Plasmas 12, 012312(2005); H. Hasegawa, K. Kato, and Y. Ohsawa, ibid. 12,082306 (2005).
5) N. Bessho and Y. Ohsawa, Phys. Plasmas 6, 3076
(1999); ibid. 9, 979 (2002).
6) S. Usami and Y. Ohsawa, Phys. Plasmas 9, 1069 (2002);
ibid. 11, 3203 (2004).

64

Analysis of Axisymmetric Equilibria with Flows in Non-Ideal Fluid Models

2. High-Beta Axisymmetric Equilibria with Flow
The second part of the work was devoted to reducedMHD models with high-beta and large-aspect-ratioorderings [2]. In improved confinement modes ofmagnetically confined plasmas where high-beta is achieved,
equilibrium flows play important roles like the suppressionof instability and turbulent transport. At the sharp boundaryof a well-confined region, the scale lengths characteristic of
microscopic effects not included in single-fluid
magnetohydrodynamics (MHD) cannot be neglected. Small
scale effects on flowing equilibria due to the Hall current
have been studied with two-fluid or Hall MHD models.
However, these models are consistent with kinetic theory
only for cold ions [1]. In order to include the hot ion effects
that are relevant to fusion plasmas, an extension of themodel is necessary. A consistent treatment of hot ions in a
two-fluid framework must include the ion gyroviscosityand other finite Larmor radius (FLR) effects. A two-fluid
equilibrium system including Hall and finite ion Larmor
radius effects was derived for flows comparable to thepoloidal Alfven velocity, showing that the ion
gyroviscosity produces a shift of the Alfven singularity. A
single-fluid system was derived for flows comparable tothe poloidal sound velocity, a case that requires keeping
higher-order terms in the aspect ratio expansion before thesingular velocity points can be shown. Since theformulation of higher-order equations is involved, here we
restricted our analysis of the poloidal-sonic flow to thesingle-fluid case, planning to extend our present resultswith the inclusion of two-fluid, hot ion effects in future
work. The singularity at a poloidal flow velocity equal tothe poloidal sound velocity was recovered in the higher
order equations. The orderings in this study provide thesimplest models that include ion FLR effects on toroidal
equilibria with flow. As such, they should be justconsidered as convenient working hypotheses that allow
our analytic study of such effects. The resulting equations
can be easily solved numerically to yield flowing equilibria
without singularity and their solutions can be used as initialstates or for comparison with saturated states of reduced
model nonlinear simulations.

Category: JIFT
Year/Number: 2005-JF1-05
Names: A. Ito (NIFS), N. Nakajima (NIFS), J.J.
Ramos (MIT)Dr. Ramos visited NIFS in the summer of 2005 andcarried out theoretical studies in collaboration with Dr. Itoand Prof. Nakajima to investigate properties ofaxisymmetric plasma equilibria with mass flows, within theframework of several non-ideal fluid models.
1. Ellipticity of Axisymmetry Equilibria with Flow and
Pressure Anisotropy
The first part of the work was based on a Hall-MHD
model with cold ions, zero-mass electrons and finite
electron pressure anisotropy [1]. This model included aclosure consistent with dynamical evolution equations forthe parallel heat fluxes and yielded a homogeneous plasma
dispersion relation identical to the one derived from kinetic
theory. The ellipticity criteria for the partial differential
equations of axisymmetric single-fluid and Hall
magnetohydrodynamic (MHD) equilibria with flow andpressure anisotropy are investigated. In the limit ofvanishing ion skin depth, it reduces to a single-fluid modelwith anisotropic pressure, which predicts mirror andfirehose instability thresholds in agreement with kinetic
theory. In the single-fluid description of plasmas,
axisymmetric toroidal equilibria with flow are obtained bysolving the so-called generalized Grad-Shafranov (GS)equation and the Bernoulli law. In the absence of poloidal
flow, the equilibrium is elliptic if the kinetic stability
conditions for the firehose and mirror modes are satisfied.
Conditions for ellipticity of the axisymmetric toroidal
equilibria with flows were derived and shown to be related
to the velocities of waves in the kinetic-consistentdispersion relation. These conditions are different fromthose for the double-adiabatic Chew-Goldberger-Low
model. For anisotropic Hall MHD, a set of anisotropicpressure equilibrium equations has been derived. It consistsof the coupled GS equations for the magnetic flux and theion stream function and the Bernoulli law for ions. Unlike
the isotropic case, in the presence of pressure anisotropy,
the characteristic determinants for each GS equation arecoupled and cannot be examined their ellipticity separately.
One can find the conditions for ellipticity of such systems
involving higher order derivatives by examining theexistence of wave type solutions, a method also applicable
to second order differential equations. If we consider awave propagating in one-dimensional space and time andhaving discontinuity across the wave front, ellipticity of thecoupled GS equations requires the non-existence of realvalues of the velocity of the wave front. A sufficientcondition for ellipticity was obtained that corresponds to apoloidal flow velocity slightly smaller than the soundvelocity.

[1] A. Ito, J.J. Ramos and N. Nakajima, “Ellipticity ofaxisymmetric equilibria with flow and pressure
anisotropy
insingle-fluidandHallmagnetohydrodynamics,” Phys. Plasmas 14, 062502(2007).
[2] A. Ito, J.J. Ramos and N. Nakajima, “High-Beta
Axisymmetric Equilibria with Flow in Reduced
Single-Fluid and Two-Fluid Models,” Plasma Fusion
Res. 3, 034 (2008).

65

Study of ballooning instability of LHD by high-accuracy numerical simulation
Category : JIFT
Year-Number : 2005-JF1-11,2009-JF-4,
Name: Hideaki Miura, S. Mahajan, W. Horton
Affiliation: National Institute for Fusion Science,*Institute for Fusion Studies (U.S.A.)
We have been studying the pressure-driven instabilityof the Large Helical Device (LHD) of National Institute for
Fusion Science, Japan, by means of numerical simulationsof MHD / extended MHD. The pressure-driven instabilities
of LHD were considered to be saturated due to thenonlinear pressure flattening mechanism of MHD. However,the understanding was base on simulations of the reduced
MHD equations with the averaging method, in which rolesof high toroidal wavenumber unstable modes and otherthree-dimensional natures were omitted.

Fig.1: Isosurface of the pressure in the MHD simulationof LHD. The flute-like structures represent growth of theballooning-modes.

In order to understand contributions of these factors,
we developed a numerical code for fully three-dimensional
compressible MHD equations, MHD In the NonOrthogonal System (MINOS). Simulations with the
MINOS code have revealed that there can be at least threemechanisms to suppress the pressure-driven instability: thepressure flattening, the compressibility effect which works
to reduce the growth rates of the unstable modes, and theparallel flow generation which releases the free energy into
the direction parallel to the magnetic field lines.1,2) In the
JIFT-JF1-11 program, we investigated these suppression
mechanisms. By the most recent numerical simulations, wehave shown that the parallel heat conduction can be much
more significant to suppress the high wave number
ballooning modes than the three mechanisms in the above.3)(In Fig.1, the isosurfaces of the pressure which are distortedby the ballooning modes are shown with the LHD CAD
image. See Ref.3.)
Recently, we have started studies on the Large Eddy
Simulation (LES) of the MHD / extended MHD system inorder to enable two requirements which contradict to eachother: taking the two-fluid effects into our simulation andshortening a computational time. In the LES approach,physical variables are filtered by an appropriate low-passfilter so that we can solve the coarse-grained equations withsmall computational costs. However, we have to develop
models of many nonlinear couplings for the purpose,
especially associated with many two-fluid effects.
Furthermore, we may need to take the effects of theparticle-field interactions into the simulation for the
purpose of numerical experiments. Because o these reasons,
there are many subjects to be solved for the purpose ofnumerical experiments with the LES approach. Some ofthese subjects are studied with the help of the JIFT program(2009-JF-4). (See Fig.2.) Some of preliminary efforts havebeen reported in Refs. 4) and 5).

Fig.2: Test particle simulations with a vortex.
1) H. Miura et al, Fusion Sci. & Tech. Vol.51 (2007) 819.
2) H. Miura et al. AIP Conference Proceedings Vol.871(2007) pp.157-168
3) H. Miura and N. Nakajima, to appear in Nuclear
Fusion (2010).
4) H. Miura and N. Nakajima, submitted to 23rd IAEA
FEC (Oct. 2010, Dajeon, Korea)
5) W. Horton, C. Correa, H. Miura, B. Rodenborn, Bull.
2009 APS April Meeting Vol.54 .

66

Energy Conversion in Magnetic Reconnection with Chaos Diffusion
Category : Fusion Physics/ Theory
Year-Number : 2006-JF1-12
Name: H. Ohtani, W.Horton*), T.Petrosky**),R.Horiuchi
Affiliation:
National
InstituteforFusion*)Science, Institute for Fusion Studies, University ofTexas at Austin, **)Center for Complex Quantum
Systems, University of Texas at Austin(i) the average orbit amplitude of the meandering
motion is determined from the location and the local
ion Larmor radii, (ii) the magnetic field changes
linearly, (iii) the size of the dissipation region isequal to the meandering amplitude, and (iv) thepressure tensor is given under a type of semi-cold
plasma approximation. Under the model, the pressure
tensor term is written as         
(1)




 
   where m is mass, B is a constant parameter of linear  = 

The present research collaboration started since
Dr. Petrosky (Center for Complex Quantum Systems,
University of Texas at Austin) stayed at National
Institute for Fusion Science (NIFS), from October2005 to January 2006 as a visiting professor. Then,the collaboration studies have been continued invarious ways. In 2007, H. Ohtani (NIFS) visited
Institute for Fusion Studies (IFS), University of Texas
at Austin, and stayed two months supported by the
JIFT program. In this stay, Prof. W. Horton (IFS)
joined in the collaboration studies. During thisopportunity, we could effectively conduct researchcollaborationson
simulationofmagnetic
reconnection. Here, we report one major result
obtained under the JIFT program.

change of B . Figure 1 shows spatial profiles ofterms of the force balance equationm 
E + (u × B) =  + (u  ) u
q t
 
1  
+ 
+
! (2)
y
qn x
and analytic solution (Eq.(1)). u is flow velocity. The
tendency of the solution (orange line) is in agreementwith the pressure tensor term(a sky blueline) of the simulation result. This result supports thatthe meandering motion plays an important role incollisionless reconnection.

Role of meandering particles in break of frozen-in
condition.
The three-dimensional particle simulation codefor magnetic reconnection in an open system,
PASMO, has been developed at NIFS. By using
PASMO code, we have intensively investigated the
dynamics and plasma instabilities in collisionlessdriven reconnection.
The plasma inflow and magnetic flux go fromthe upstream toward the center region because of thedriving electric field imposed at the upstream
boundary. The driving field penetrates into the current
sheet owing to particle kinetic effects, and triggers
magnetic reconnection when it reaches the center.
In the ion dissipation region around the central
reconnection point at which collisionless reconnection
sets under the influence of driving flow, the frozen-in
condition is broken by the pressure tensor term     
 

Fig. 1. Spatial profiles of terms of the force balance
equation (Eq.(2)) for ion and analytic solution(Eq.(1)) of   along y direction through thereconnection point. Red, green, blue, magenta, sky(u × B) ,blue and orange lines show E ,(Fig.1), where q is charge, n is numberm(u)u #q,

density,  is pressure tensor. Pressure tensor term
originates from the stochastic thermal motion called
meandering in the vicinity of reconnection point. We
examined the relationship between the meandering
motion and the pressure tensor based on a simple
model (Ref.(1)). In the approximations of the model,     ,in the simulation result,
 
 
  

and analytic solution of , respectively.

1) H.Ohtani, W.Horton, T.Petrosky and R.Horiuchi:
J. Plasma Fusion Res. SERIES, Vol.8, (2009),
pp.203-207.

67

Plasma rotation effects on resistive wall mode stability and magnetic island formation by error fields

Category: Joint Institute for Fusion Theory
Year-Number: 2006-JF1-11, 2007-JF1-5, 2008-JF1-6
Name: Masaru Furukawa1), Linjin Zheng2)
Affiliation: 1) Grad. Sch. Frontier Sci., Univ. Tokyo,
2)
Inst. Fusion Studies (IFS), Univ. Texas at Austin

layer has an infinitely thin width. Advantages are: i) it isapplicable to reversed magnetic shear configuration with its
minimum safety factor being a rational number, ii) highaccuracy can be obtained because of the avoidance ofnumerical treatment of singularity, iii) it can be formulated
easily as an initial-value problem and so on. Our technique
has been applied to well-known results of single anddouble tearing, internal kink and interchange modes in acylindrical geometry, and the results have shown its good
performance.
We have also discovered a new instability, “currentinterchange tearing mode”, in the presence of resistivity
gradient3). Figure 2 shows the mode structure. We see that\ 2/1 is finite at the rational surface r=0.5, i.e., magnetic
islands are generated.

High-beta and long-pulse discharges of tokamak
plasmas have introduced serious problems of disruption
and confinement degradation due to relatively slow MHD
phenomena such as resistive wall mode (RWM) andneoclassical tearing mode (NTM). These are important
issues not only as the nuclear fusion development, but also
as physics problems. It was shown experimentally that theRWM can be stabilized if the plasma is rotating toroidally
and that the critical rotation speed for the stabilization isclosely related to externally given error fields. In addition,
this error field penetrates and can be amplified in theplasma, which generates magnetic islands at the rationalsurface. Thus the error field is also closely related to NTM.
Therefore, these problems cannot be divided into elements.
The motivation of our study is therefore to develop
theoretical models and analysis methods on the RWM
stability and the generation of magnetic islands due to theerror fields under the presence of plasma rotation, and toverify the models by numerical simulations.
We have studied the effect of plasma rotation on thepenetration of error fields into the plasma by low-beta
reduced MHD simulation in a cylindrical configuration.1)
The plasma rotation and the error field at the plasma edge
are kept unchanged, and we observed stationary states after
transient dynamics. If the equilibrium rotation changes
slowly, the plasma may follow a sequence of the quasistationary states obtained in the simulation. Figure 1 shows
the magnitude of the penetrated magnetic flux |\ 2/1 (r s )|versus the rotation speed v Ts at the rational surface. We seethat |\ 2/1 (r s )| or the island width begins to decrease rapidly
as v Ts is increased above some critical value, and that thecritical value is lower for smaller resistivity K. This isbecause two current sheets, generated at the Alfvén
resonances which are at both sides of the rational surface inthe presence of plasma rotation, have enough shielding
effect on the penetration of error field if the current sheets
do not overlap the rational surface when the rotation speed
is fast enough. This situation occurs at lower rotation speed
for smaller K. We also calculated the electromagnetic
torque generated by the penetrated error fields, whichbrakes the plasma rotation. In the range of fast rotation, thetorque is proportional to v Ts , and does not depend on K.
It is difficult actually to apply the conventional
asymptotic matching method to the situation where thecurrent sheet splits fully into two sheets. In order to resolve
this, in addition to some practical difficulties inherent in theasymptotic matching method, we have developed a newmatching technique2). Our new technique is a direct
matching using the inner layer with a finite width. In thematched asymptotic expansion, on the contrary, the innerFig.1. Magnetic flux of the penetrated error field |\ 2/1 (r s )|versus the rotation velocity at the rational surface.

Fig.2. Mode structure of newly-discovered “currentinterchange tearing mode”.
1) M. Furukawa and L. –J. Zheng, Nucl. Fusion 49(2009) 075018; The 22th IAEA Fusion Energy Conference,
TH/P9-13 (2008).
2) M. Furukawa, S. Tokuda and L. –J. Zheng, submitted
to Phys. Plasmas (2009); The 50th Ann. Meeting Div.
Plasma Phys., American Phys. Soc., CP6.73 (2008).
3) L. –J. Zheng and M. Furukawa, Phys. Plasmas (accepted,2010) ; L. –J. Zheng and J. W. Van Dam, The 51th Ann.
Meeting Div. Plasma Phys., American Phys. Soc., UP8.84(2009).

68

JIFT Workshop on Gyrokinetic Simulation of Plasma Transport

Category: JIFT
Year/Number: 2007-JF1-1
Names: T. S. Hahm (PPPL), H. Sugama (NIFS)
This workshop was held at the High Temperature
Plasma Center, Kashiwa Campus, The University of Tokyo,
September 24 and 25, 2007.
The workshop consisted of 4 sessions: (I) Recent
Progress in Gyrokinetic Simulation, (II) Theory andExperiments on Momentum Transport, (III) Theory and
Simulation of Electric Fields and Flows, and (IV) MultiScale Physics, New Fluid Simulation.
In addition, there was a special lecture entitled“Plasma Waves and Instabilities in Shear Flow–A Frontierof Functional Analysis beyond von Neumann’s Theorem.”Talks were presented by 11 scientists from Japan, 2 fromUS, and 2 from EU. Recent results from theoretical andsimulation studies about plasma transport based on
gyrokinetic and gyrofluid models were reported.
Comparative studies of theoretical modeling andexperimental results of toroidal momentum transport intokamaks and helical systems were made. Also, topics suchas zonal flows, geodesic acoustic modes, and multi-scaleinteractions in ion temperature gradient (ITG) turbulence
were discussed.
Several papers that were subsequently publishedacknowledged simulating scientific exchanges during thisworkshop. One such paper [1] presented a refined
formulation of the gyrokinetic equations for plasmas withlarge flow shears caused by an equilibrium electric field.
Through the choice of a more suitable equilibrium drift
velocity for the reference frame of a charge particle, theaccuracy of the gyrokinetic equations can be significantly
improved. Another paper [2] showed the derivation of anenergy conserving set consisting of the fully
electromagnetic nonlinear gyrokinetic Vlasov equation andMaxwell’s equations, where this set of equations isapplicable both to L-mode turbulence with large amplitude
and to H-mode turbulence in the present of large ExB shear.
A third paper [3] described how plasma parameter scans—such as the plasma current, neutral beam heating power,
and electron density—had been used to obtain properties of
the toroidal momentum diffusivity and the convection
velocity in H-mode plasmas in the JT-69U experimental
facility.

Fig. 1. Time evolution of the particle energy as calculatedwith a refined version of the gyrokinetic equations forlarge flow shear, compared to the previous analysis of
Qin [from Ref. 1]

Fig. 2. Comparison of the pinch velocity from modulation
experiments in JT-60U with that calculated from twotheories [from Ref. 3][1] G. Kawamura and A. Fukuyama, “Refinement of the
gyrokinetic equations for edge plasmas with large flow
shear,” Phys. Plasmas 15, 042304 (2008).
[2] T.S. Hahm, Lu Wang, and J. Madsen, “Fullyelectromagnetic nonlinear gyrokinetic equations fortokamak edge turbulence,” Phys. Plasmas 16, 022305(2009).

[3] M. Yoshida, Y. Kamada, H. Takenaga, et al.,“Characteristics of momentum transport in JT-60U Hmode plasmas,” Nucl. Fusion 49, 115028 (2009).

69

Relativistic Fast Electron Transport in Fast Ignition Targets
Category : Joint Institute for Fusion Theory
Year-Number : 2007-JF1-10
Name: T. Johzaki, Y. Sentoku*
Affiliation: Institute of Laser Engineering, Osaka
University, *University of Nevada, Reno

beam Intensity [W/cm2]

is also comparable. Thus, the increases in electron and ion
temperatures in the core ('<T e > and '<T i >) are twice
larger in the CH cone case because of larger conversion
efficiency from laser to hot electrons.

In Fast ignition using cone-guide targets, the coreheating is done by the energy transport of fast electrons
generated at the cone inner surface. In Fast Ignition
Realization Experiments phase-I (FIREX-I), the heating
laser energy is 10kJ and it will be 100kJ in the fusion
reactor. When using such a high energy heating lasers, thebulk electron temperature in the cone tip becomes higher
than 10keV due to laser irradiation and fast electron heating,and Au atoms reach highly-ionized state. In such a situation,
the fast electron generation and its transport will be affectedby the collisional processes in cone tip. So we haveestimated the dependence of core heating properties on thecone tip material on the basis of coupled 1D simulations;collisional/ionization particle-in-cell (PIC) simulations forintense-laser plasma interactions and Fokker-Planck (FP)simulations for fast electron transport and core heating.
The fast electron profiles obtained from the PIC
simulations for Au and CH cone tips are shown in Fig.1. It
is found that a high-Z Au has disadvantages as a conematerial in the long-duration and high-intensity laser case.
The atoms rapidly reach highly-ionized states. In particular,
the ions around the interaction region reach nearly fullionization within a few hundreds fs. Because of the density
profile steepening and the resistive damping of returncurrent after reaching highly-ionized state, the conversion
efficiency of laser to hot electrons decreases. In addition,
the electron beam quality deteriorates due to the collisionaland resistive drags and the scattering by the ions even for
10Pm propagation in the Au cone tip. As a possible way to
improve the energy coupling and to reduce the collisional
effects, we propose to use a low-Z material (CH) as a cone
tip material. The resistive damping of return current is weakfor the CH case and the energetic electrons arecontinuously supplied into the LPI region. Thus the highbeam intensity is kept even after the density steepening
occurs. In addition, the scattering of fast electron beam isalmost negligible. Therefore, twice higher energy couplingof laser to fast electron is obtained.
Using the fast electron profiles obtained from the PIC
simulations, the core heating properties were evaluated with
the FP simulations, where the cone tip thickness is 10Pm
(20Pm) for Au cone (CH cone). The temporal evolution ofcore temperature is shown in Fig.2, and the core heating
properties are summarized in Table I. Compared to the Au
cone case, the energy coupling of the heating laser to thefast electron is twice higher in the CH cone. Though the
propagation length is twice longer in the CH case, theenergy ratio of the deposition in the cone to the beamsource is comparable between the CH and Au cases. Theenergy ratio of the deposition in the core to the beam source

1E20

CH target (E>0.1MeV)
Au target (E>0.1MeV)

(a)

1E19

1E18
0.0

0.2

0.6

(b)

1E21

f(E)

0.4

0.8

1.0

Time [ps]1E22

CH target
Au target

1E20
1E19
1E18
1E17

0

1

2

3

4

5

6

7

8

Energy [MeV]

THWHM [degree]

60
50

(c)

㩷㪘㫌
㩷㪚㪟

40
30
20
10
0.1

1

Energy [MeV]10

Fig.1. Comparison of observed fast electron profiles
between Au and CH cone tips. (a) Beam intensity, (b)energy spectrum and (c) angular spread (full width at half
maximum of angular distribution). In both cases theionization is considered.

<T> [keV]

0.45

0.40

0.35
<Te> <Ti>
CH coneAu cone

0.30
0.0

0.5

1.0

1.5

2.0

2.5

Time [ps]Fig.2. Temporal evolution of averaged electron (red) andion (blue) temperatures in the core region (U > 1 g/cm3).
The solid lines stand for the CH cone case, the dashed lines
for the Au cone case..
Table I. Comparison of core heating properties
Au coneCH coneSource energy [MJ/cm2]
7.34
15.26
Edep in cone* [MJ/cm2]
0.78
1.53
1.62
3.57
Edep in core* [MJ/cm2]
0.057
0.13
ǻ<Te> [keV]
0.055
0.11
ǻ<Ti> [keV]*70

Edep is deposited energy of fast electrons

Simulation Study of the ICRF Minority Heatingin the Quasi Helically Symmetric Plasma
Category : JIFT
Year-Number : 2008-JF1-7
Name: S. Murakami, K. Likin∗ , J. Talmadge∗
Aﬃliation: Dpt. of Nuclear Eng., Kyoto Univ.
∗
HSX Plasma Laboratory, Univ. of Wisconsin
In HSX plasma the ECH experiments have been
performed and a clear improvement of the electron
temperature in the quasi-helically symmetric (QHS)
conﬁguration is observed because of the reduction of
the neoclassical transport. Also the trapped particle
orbit is improved in the QHS conﬁguration. However, when the energy of particle increases the orbitof the trapped ion becomes complex due to the ﬁnite ripple ﬁeld and ﬁnite orbit eﬀect; e.g. the ion
orbit of 10keV shows a stochastic trajectory. On
the other hand ICRF heating is considered as anadditional heating method in HSX to heat both ofelectrons and ions. Thus the detail analysis of the
ICRF heating eﬃciency is necessary to set up the
ICRF heating system.
We study the ICRF minority heating in the QHS
conﬁguration of HSX applying GNET code[1]. The
eﬃciency is evaluated assuming the heating powerof 100kW. We consider the ICRF sustained plasma
and the plasma parameters are as follows: the electron and ion temperature: Te0 = Ti0 = 200eV, theplasma density: ne0 = 2 × 1019 m−3 , and magnetic
ﬁeld strength: B0 = 2.0T.
First we run the GNET with a relatively large
RF wave electric ﬁeld (about 2.5kV/m) and heatingeﬃciencies are evaluated after a short time changing
the resonance magnetic ﬁeld strength. It is foundthat the obtained heating eﬃciency show an optimum when Bres /B0 ∼ 1.02. We apply the eﬀective
conﬁnement region and results are shown in Fig. 1.
We can also see an optimum point in Bres space inboth conﬁnement region cases (ref f /a = 0.66 and
0.8).
Next we study the ICRF heating in HSX running the full simulation assuming the optimum Bres .

30

Fig. 1: Heating eﬃciencies assuming the eﬀective
conﬁnement minor radius in the HSX.
[1] S. Murakami, et al., Nucl. Fusion 46, S425
(2006).

30

60
50
40
30
20
10
0

25
20
15
10

Figure 2 shows the evaluated minority ion distribution in the velocity space at the three r/a points;
r/a = 0.1 − 0.25 (left), r/a = 0.5 (center) and
r/a = 0.75 (right). Large tail formation is observedin the resonance surface region and Up to 40keV
energetic ions are obtained. Lost ion distribution
shows broad proﬁle in the pitch angle space compared with that of the LHD. This indicates that theloss mechanism is diﬀerent from that of LHD, where
the transition between the trapped and passing particles plays important role.
Radial proﬁles of the power absorption shows astrong peak near the resonance layer but the energetic ion pressure and the heating deposition show
broader proﬁle due to the ﬁnite orbit eﬀect. This
also indicates the existence of a large radial diﬀusion due to the ﬁnite orbit eﬀect.
As a results we obtain the following heating efﬁciency, η,; P ∼ 58kW η = 0.47 and P ∼ 97kW,
η = 0.34. Also we found that the neutral density changes the heating eﬃciency about 10% andmore detail simulation should be done to evaluate
the heating eﬃciency correctly.

20
15
10

v⊥ / vth0

5
-15

-10

-5

0
v// / vth0

5

10

15

20

20
15
10

v⊥ / vth0

-15

-10

-5

0

5

v// / vth0

10

15

20

v⊥ / vth0

5

0
-20

60
50
40
30
20
10
0

25

5

0
-20

30

60
50
40
30
20
10
0

25

0
-20

-15

-10

-5

0

5

10

15

20

v// / vth0

Fig. 2: Minority ion distribution in the velocity space in the HSX at the three minor radius points;
r/a = 0.1 − 0.25 (left), r/a = 0.5 (center) and r/a = 0.75 (right).

71

Simulation study of neoclassical transport in non-axisymmetric plasmas using the G f method
Category : JIFT
Year-Number : 2008-JF1-8
Name: Shinsuke Satake, Weixing Wang*
Affiliation: National Institute for Fusion Science,Princeton Plasma Physics Laboratory*

width effect is unimportant, it is profitable to make anumerical way of solving the drift-kinetic equation using
the G f method in the zero-orbit-width limit. Satake hadfound the accumulation of numerical error in simulation
marker energy when the numerical scheme of zero-orbitwidth limit calculation, which Dr. Wang had demonstrated
in tokamak cases, was applied to non-axisymmetricconfigurations. They discussed about how to improve thenumerical scheme, and the result of the study was finallypresented at the JPS meeting2) 2009.
While visiting PPPL, Satake had a proposal of applying
FORTEC-3D to calculate neoclassical toroidal viscosity(NTV) of NSTX, a spherical tokamak device in PPPL. At
that time, ELM control experiments in some tokamaks
including NSTX by means of external non-axisymmetricmagnetic field perturbation had attracted attention.
However, it was concerned that the neoclassical viscositythat arises from the break of symmetry might affect the
MHD stability such as resistive wall mode, and aquantitatively reliable method to calculate NTV in weaklyperturbed tokamaks had been required. Then, Satake began
discussion and collaboration with Drs. W. Wang, A.
Boozer, J.-K. Park and S. Sabbagh, and a new numericalformulation to calculate NTV directly from FORTEC-3D
code had developed. This research has continued since then,and preliminary benchmark result was presented at the
ISHW 2009 workshop held in PPPL4). The collaborative
research activity of NTV simulation with PPPL researchers
is still going on. Visiting PPPL as a JIFT program wasreally a good opportunity to start a new collaboration.

Neoclassical transport theory describes the irreducible level of particle and heat transport in torus
plasma and constitutes the basis of transport analysis infusion devices. Compared with that in axisymmetrictokamaks, neoclassical transport in non-axisymmetricconfiguration as LHD in NIFS is more complicated owing
to these two effects as follows; the one is the enhancementof radial drift of the particles which are trapped in local
magnetic ripples, and the other is the effect of the radial
electric field. Different from the tokamak cases in which theneoclassical particle flux is intrinsic ambipolar, the radial
drift of ripple-trapped particles is strongly affected by the
ExB rotation, and the radial electric field develops
spontaneously so that ion radial particle flux balances thatof electrons. This ambipolar electric field condition has
multiple roots in some cases, depending on the magnetic
configuration and profiles of plasma density andtemperature. The neoclassical transport level largely
changes according to which ambipolar root is realized inplasma.
In order to solve neoclassical transport in nonaxisymmetric plasmas with high accuracy, it is required to
calculate the guiding-center motion with precise magnetic
field description in magnetic coordinates, to introduce a
Coulomb collision operator which satisfies its conservation
low, to consider the radial electric field profile which
satisfies the ambipolar condition, and so on. Satake hasdeveloped a simulation code FORTEC-3D1) which solves
neoclassical transport and evolution of radial electric field
for non-axisymmetric configuration. To improve thenumerical schemes in the code and to promote neoclassicaltransport analysis using FORTEC-3D in other devices than
LHD, Satake visited Dr. Weixing Wang in PPPL, who had
developed the original G f method, from Oct. 22 to Dec.
22, 2008.
When Satake applied for the JIFT program, the nonaxisymmetric plasma confinement device NCSX was underconstruction in PPPL. Therefore, one of the main subject
was the application of FORTEC-3D code to NCSX
magnetic configurations. However, the NSCX project wassuspended just before the visit. Then at the beginning ofvisit, Satake discussed with Dr. Wang about the numerical
scheme of the G f method. FORTEC-3D is a global
transport code which solves the drift-kinetic equation in thewhole plasma confinement region at once. And it includes
the higher-order terms of the finite-orbit-width effect,
which stems from the radial excursion of guiding-center
orbits. However, to compare with conventional local
analyses of neoclassical transport or to evaluate the electron
neoclassical transport coefficients in which the finite-orbit-

q=7/3

Fig.1 : An example of NTV calculation on tokamak with small
perturbation magnetic field. On the q=7/3 surface where theperturbation field resonates with background magnetic field,
peaking of NTV is found. And the magnitude of NTV is found to
be proportional to the square of the magnitude of field
perturbation, GB .
2

1) S. Satake et al, Plasma Fusion Res. 3, S1062 (2008).
2) S. Satake et al, oral presentation at the 64th annual
meeting of the Physical Society of Japan, Mar. 27th, 2009.
3) W. Zhu et al, Phys. Rev. Lett. 96, 225002 (2006)4) S. Satake et al, “Calculation of Neoclassical Toroidal
Viscosity in Tokamaks with Broken Toroidal Symmetry”,
ISHW2009 , PPPL Oct. 13, P02-21.

72

Reduced Nonlinear Dynamics for Turbulent Transport
In Toroidal Confinement Devices
Category: JIFT
Year/Number: 2008-JF1-12
Names: W. Horton (IFS Texas), H. Sugama (NIFS),
T.-H. Watanabe (NIFS)
In about 2000, we became interested in new techniques
to analyze ion temperature gradient (ITG) driven
turbulence. For the infinite chain of linked fluid transport
equations, we wanted to find a fluid closure that would
reproduce the most important aspects of the full gyrokinetic
equations. In the 1990s, we had completed a series ofstudies of fluid turbulence theory and simulations for the
resistive-g mode and the Hasegawa–Wakatani drift wave
model. Our fluid simulations showed that nonlinear
interactions in the unstable spectrum produced sheared
azimuthal ExB flows and an oscillation in the parallel
thermal flux. The question was how to find an accurate
ITG gyrofluid model.
We wanted a new closure procedure with parallel heat
fluxes that would give accurate nonlinear energy
conservation laws and correct entropy production functions.
Using the unstable Vlasov-Poisson ion temperature
gradient (ITG) modes, we searched for closures that
reproduced the unstable and stable spectra. This implied
preserving the time-reversal symmetry of the collisionless
kinetic equation. After studying the closure of Mattor andParker (1997), we eventually found a closure that preserves
time reversibility and whose unstable-stable spectrum
agrees fairly well with that from the plasma dispersion
function of the exact kinetic equation. The key point is thatthe new non-dissipative collisionless closure method
enabled the very accurate calculations of the parallel
thermal flux driven by temperature fluctuations that are
required.
Our result [1] led to a series of simulations andderivations of reduced gyrofluid equations [2]. The mostrecent concerned zonal flows driven by turbulence [3],simulated with the GKV code.
The GKV code of Sugama and Watanabe is now
widely used for turbulence simulations. It solves for thefluctuation distribution function directly on high-resolution
parallel velocity grids, which allows accurate tracking of
the phase and amplitude of higher order parallel velocity
moments. Comparison with the Hammett-Perkins closure
showed that the GKV solutions reproduce the radial
turbulent thermal flux more accurately.
During Horton’s three-month visit to NIFS in 2007 as
the JIFT Visiting Professor, the GKV code wasbenchmarked on several large-scale parallel computers,
including Ranger at the University of Texas and Blue Geneat ORNL. The code showed good linear scaling with thenumber of processors.
This joint work is continuing. The new closure models
are now being used in the pseudo-spectral simulations with
ion-temperature-gradient and electron-temperature-gradientturbulence gyrofluid models.

Fig. 1. Time evolution of the zonal flow potential,
comparing kinetic and fluid results, as functions of (a)time and (b) wave number. [from Ref. 3][1] H. Sugama, T.-H.Watanabe, and W. Horton,“Collisionless kinetic-fluid closure and its application
to the three-mode ITG system,” Phys. Plasmas 8, 2617
(2001).
[2] H. Sugama, T.-H.Watanabe, and W. Horton,“Comparison between kinetic and fluid simulations ofslab ITG driven turbulence,” Phys. Plasmas 10, 726(2003).
[3] H. Sugama, T.-H.Watanabe, and W. Horton,“Collisionless kinetic-fluid model of zonal flows intoroidal plasma,” Phys. Plasmas 14, 022502 (2007).

73

Anisotropic Pressure Diffusion in the HINT Codeconsistent set of equilibrium equations is then described.
Some algorithmic approaches aimed at solving theseequations were investigated.
There is nothing radical about approximating an ideal
MHD equilibrium by a resistive steady state, but we havecome to this conclusion by considering the impact ofchaotic fields on MHD equilibria, and requiring that thepressure be continuous. Since the equilibrium solutions arepathological when the field is chaotic, a nearly-ideal,
resistive steady state equilibrium is the simplest model
capable of computing coherent, self-consistent MHD
equilibria with continuous (and non-fractal) pressure. Work
towards implementing the anisotropic pressure diffusion
into the HINT code has begun. Our approach, which is bothcomputationally efficient and consistent with the structureof the HINT code, is to use locally field aligned
coordinates that separate the large parallel transport fromthe small perpendicular transport, and thus reducs so-called“numerical diffusion.” We hope to present computational
results in the near future.

Category: JIFT
Year/Number: 2009-JF-9
Names: S. Hudson (PPPL), N. Nakajima (NIFS)
Dr. Hudson from PPPL spent three months at NIFS as
the JIFT Visiting Professor (summer 2009). During thistime, he performed research in collaboration with Dr. N.
Nakajima concerning how to realistically and efficiently
compute MHD equilibria in the presence of chaotic
magnetic fields.
Analyses of plasma behavior often begin with adescription of the ideal magnetohydrodynamic equilibrium,
this being the simplest model capable of approximating
macroscopic force balance. For perfectly axisymmetrictokamaks this is a comparatively simple task, since a nested,
continuous family of flux surfaces exists, i.e. the field is
integrable. The ideal equilibrium equation can be reduced
to the Grad-Shafranov equation, and equilibria can befound numerically. In contrast, for stellarators andperturbed tokamaks, the magnetic fields are generally nonintegrable and a different approach is required.
Stellarators are designed to have good flux-surfaces,
but without a continuous symmetry, perfectly integrable
fields cannot be achieved. The HINT and HINT2 codesdeveloped at NIFS, and the PIES code developed at PPPL,
seek solutions to the ideal force balance equation instellarator geometry without assuming a nested family offlux surfaces. HINT uses a relaxation algorithm, whereas
PIES is based on an iterative scheme with magnetic
coordinates. However, neither code adequately treats thefractal structure of pressure in a chaotic field.
A generally chaotic field will be a fractal mix of KAM
surfaces, islands, and irregular field lines. Some field lines
trace out structures that are infinitely complex, such as theunstable manifold. Interspersed between these irregularfield-lines are periodic orbits; arbitrarily small, high-orderisland chains; and irrational field-lines, which may or may
not trace out smooth flux surfaces. Generally, there is noregion of space foliated with flux surfaces and magnetic
islands and irregular field-lines will emerge at the infinitely
many rational surfaces that exist between any pair of KAM
surfaces. When the field is chaotic, it is extremely difficult
to calculate the ideal MHD equilibrium.
In ideal force balance, the structure of the pressure istied to the structure of the field. Thus, a continuous,
nontrivial pressure has an uncountable infinity of
discontinuities in the pressure gradient. The equilibrium
solutions are pathological when the fields are chaotic andtherefore unsuitable for numerical calculations.
If the pressure and magnetic field are continuous, theonly nontrivial solutions have an uncountable infinity of
discontinuities in the pressure gradient and current. The
problems arise from the arbitrarily small length scales inthe structure of the field, and the consequence of ideal
force balance that the pressure is constant along the fieldlines. A simple method to ameliorate the singularities is toinclude a small but finite perpendicular diffusion. A self-[1] S. R. Hudson and N. Nakajima, “Pressure, chaotic
magnetic fields, and magnetohydro-dynamic
equilibria,” Phys. Plasmas 17, 052511 (2009).

74

CHAPTER 5JUPITER-II࣭TITAN

5.1 Progress in US-Japan collaboration research
The US-Japan collaboration was started in FY 1981, and the first phase was the RTNS-II (Rotating
Target Neutron Source-II) project, followed by the second phase known as the FFTF/MOTA (Fast
Flux Test Facility/Materials Open Test Assembly) project from FY 1987. In the RTNS-IIprogram, fusion neutron irradiation experiments using the D-T neutron source of the U.S.A. werecarried out. Though the maximum irradiation dose was about 0.1dpa, Japanese advanced
technologies on microstructure observation by electron microscopy and material strength
evaluation by testing miniaturized specimens were utilized to obtain wide and highly precise dataon the generation and accumulation processes of defects induced by the D-T neutrons as well as on
the microstructure-strength correlation. The results from these experiments are still very valuable
even now. The main theme in the FFTF/MOTA project was to explore the effects of high-dose neutron
irradiation up to 100dpa, which was the expected life time for fusion reactor materials. A more
fundamental approach, compared to conventional irradiation tests, was promoted and a thoroughunderstanding of the entire microstructural evolution process under irradiation covering low dose
to high dose irradiation regimes was obtained.
The irradiation experiments in the above projects were performed under relatively simple andsteady irradiation conditions. The JUPITER project focused on dynamic irradiation effects
detectable only during irradiation and effects of variable and combined irradiation conditions. This
included radiation-induced conductivity of ceramic insulators, varying temperature effects, andcombined transmutation effects. These experiments extracted valuable information on materials
response in fusion relevant environments.

5.2

Objectives, research subjects and facilities

5.2.1 JUPITER-II project(FY2001-2006)

The projects before JUPITER-II focused on materials performance under irradiation and materials
development based on the knowledge gained from the irradiation experiments. In fusion blankets,materials will be used as joined or coated materials (materials systems). In addition, the use ofmaterials in blankets involves new issues associated with the interaction with breeders and coolants.
Thus basic technological studies and their integration are essential. The issues are better specified
with the progress in the blanket design.
JUPITER-II project aimed at (1) developing key technology for fabrication and operation of“self-cooled liquid blankets” and “high temperature gas-cooled blankets” which are combinationsof low activation structural materials and breeder/coolants which are capable of high tritium
breeding ratio and high coolant exit temperature, and (2) evaluation of the irradiation performanceof the materials system which is a key feasibility issue for blanket development. Overall evaluationof blankets and materials systems based on modeling, and orientation of the development towards

75the commercialization of the system were also carried out in this project.
5.2.1.1

Research subject and task structure of JUPITER-II

Table 5-1 summarizes research subjects and task structure of JUPITER-II project.
5.2.1.2

US facilities used(a) STAR (Safety and Tritium Applied Research) [INL]STAR was established at the Idaho National Laboratory in 2001, having an allowable tritium
inventory of 16,000 Ci. The site includes the Tritium Plasma Experiment (TPE) and various
facilities for testing tritium behavior in blanket conditions. Unique features of the facility include
use of large amounts of tritium, Be, and neutron-irradiated materials.
(b) HFIR (High Flux Isotope Reactor) [ORNL]HFIR is a 100MW mixed spectrum research reactor, currently operated at 85MW, that is currently
planned to remain in operation until 2035. Although the principal purpose of the reactor is to
produce radioisotopes, it is actively used for materials irradiation and neutron scatteringexperiments utilizing the world’s highest fast and thermal neutron fluxes. The HFIR is a unique
irradiation facility with the potential for high environmental and temperature control during
irradiation, and very low to high flux irradiation. Parts of the HFIR-irradiated specimens wereshipped to Oarai Center of Tohoku University for Post Irradiation Examinations.
(c) MTOR (Magneto-Thermofluid
Omnibus Research Facility)[UCLA]
The facility includes a magnet ofhomogeneous field to 2T in an area
15cm wide and 1m long, which can beused for testing the fluid dynamics ofliquid metals and MHD flow for highPrandtl number stimulant fluids using
electrolytes.

5.2.2 TITAN project(FY2007-2012)
Blankets are component systems
whose
principal
functionsareextraction of heat and tritium. Thus itis crucial to clarify the potentiality forcontrolling heat and tritium flow
throughout the first wall, blanket andout-of-vessel recovery systems. The
TITAN
project
continues
theTable 5-1 Task structure of JUPITER-II project
Task

Subtask

Activity

1-1:
Task1:
Self-Cooled FLiBe Cooled
LiquidBlanket

1-1-A: FLibe
Handling/Tritium
Chemistry/Safety

Purification,transport, REDOX
control and tritium
behavior

1-1-B: FLibe
Termofluid
Flow
Simulation

Thermofluid of Flibe
simulant

1-2:
Li Cooled with V
Alloy Structure

1-2-A: Coatings MHD insulator
coating for Li/V
for MHD
blanketReduction
1-2-B: V Alloy
CapsuleIrradiation

Task2:HighTemperatu
re GasCooled
Blanket2-1: SiC
Task2:
Fundamental Issues, HighFabrication, andTemperature
Material Supply
Gas-Cooled
Blanket2-2: SiC System
Themomechanics
2-3: SiC Capsule
Irradiation

Task3:
Blanket
SystemModeling

76

3-1: Design-based
Integration
Modeling
3-2: Material
Systems Modeling

Irradiation of
vanadium alloys in Li
capsuleFabrication
technology of SiC/SiC
Thermomechanics of
He cooled blanket
High temperatureirradiation of SiC/SiC

Task3:
Blanket System
Modeling

Integration model foradvanced blankets
Multi-scale materials
modeling

Table 5-2 Task structure of TITAN project
Task
Task 1
Transport
phenomena

Task 2
Irradiation
synergism

Common Task
Systemintegration
modeling

Subtask

Facility

Goal

1-1 Tritium andmass transfer infirst wall

TPE
PISCES

Mass transfer and tritium
inventory in first wall, and tritiumtransfer between first wall andblanket

1-2 Tritium
behavior inblanket systems

STAR

Tritium transfer in blanket
elements

1-3 Flow control
and thermofluid
modeling

MTOR

Thermofluid in high magnetic fieldand comparison between
experiments and modeling

2-1 Irradiationtritium synergism

HFIR
STAR

Neutron irradiation effects on
tritium transfer in first wall andstructural materials

2-2 Joining andcoating integrity

HFIR

Radiation response of joint andcoated materials, and synergistic
tritium and helium effects

2-3 Dynamic
deformation

HFIR

Deformation of structural materials
during irradiation, and effects oftritium and helium production

MFE/IFE system
integration
modeling

Integrate modeling of mass andheat transfer in first wall, blanket
and recovery system, andcontribution to reactor systemdesignJUPITER-II activity but extends its scope including the first wall and the recovery systems with thetitle of “Tritium and thermofluid control for magnetic and inertial confinement systems”. The
objective of the program is to clarify the mechanisms of tritium and heat transfer throughout thefirst-wall, the blanket and the heat/tritium recovery systems under specific conditions to fusion
such as irradiation, high heat flux, circulation and high magnetic fields. Based on integrated models,
the breeding, transfer, inventory of tritium and heat extraction properties will be evaluated for some
representative liquid breeder blankets and the necessary database will be obtained for focusedresearch in the future.
5.2.2.1

Task structure and research subjects of TITAN project

The JUPITER-II project confined its scope to blankets and enhancement of key technologies. The
TITAN project seeks to further enhance key technologies and to conduct system integration fortritium and heat transfer in the first-wall, blanket and recovery systems. Table 5-2 summarizes task
structure of TITAN project.
5.2.2.2

US facilities used

The following facility is being used for the TITAN project in addition to the facilities used during
the JUPITER-II project.
(d) PISCES(Plasma Interactive Surface Component Experimental Station)[UCSD]

A linear plasma simulator which can produce high-density plasmas with H, D, He and Be. Pulsed
lasers are equipped for synergistic plasma exposure and pulse heating studies. Plasma diagnostics
and surface characterization systems are furnished.

77

Table5-3 Administration structure of JUPITER-II project
Steering Committee
Representative S. Berk/G. Nardella (DOE)

Representative K. Abe (Tohoku U.)
Coordinator

A. Kohyama (Kyoto U.)

Coordinator S.J. Zinkle (ORNL)
D.K. Sze (UCSD)

S. Tanaka (U. Tokyo)
Japan

Task
Task1:
1-1:
Self-Cooled FLiBe
LiquidCooledBlanket

1-1-A: FLibe Handling
Chemistry/Safety/Tritium

1-1-B: FLibe Termofluid Flow
Simulation

1-2:
Li Cooledwith V
Alloy
Structure

USTC

DeputyTC

DeputyT. Terai

K. Okuno/
M.
NishikawaD.A. Petti

R.A. Anderl

S. Toda/T. Kunugi

T. Kunugi/
T.Yokomine

M.A. Abdou

N. Morley

1-2-A: Coatings for MHD Reduction

T. Muroga
T. Muroga

1-2-B: V Alloy Capsule Irradiation

H. Matsui

Task2:
2-1: SiC Fundamental Issues,
High-Temperature Gas- Fabrication, and Material Supply
Cooled Blanket
2-2: SiC System Themomechanics

A.
Hasegawa A. Shimizu

G.R. Odette

Y.Katoh

T. Hinoki

2-3: SiC Capsule Irradiation
Task3:
Blanket System
Modeling

B.A. Pint
R.J. Kurtz

R.H. Jones/ L.L.
Snead

A. Hasegawa

3-1: Design-based Integration
Modeling

A. Sagara

3-2: Material Systems ModelingH.
Hashizume

A. Ying
L.L. Snead
D. SzeN.M. Ghoniem

N. Sekimura

R.E. Stoller

Table 5-4 Administration structure of TITAN project
6WHHULQJ&RPPLWWHH
5HSUHVHQWDWLYH .2NXQR‫ق‬6KL]XRND8‫ك‬

5HSUHVHQWDWLYH *1DUGHOOD‫'ق‬2(‫ك‬&RRUGLQDWRU '.6]H ‫ق‬8&6'‫ك‬&RRUGLQDWRU70XURJD‫ق‬1,)6‫ك‬Task

SubtaskTC (JP)

STC/Deputy (JP)Task 1
Transport
phenomena

1-1 Tritium andmass transfer infirst wall

T. Terai(U.Tokyo)Y. Ueda (Osaka U.)/
N. Ohno (Nagoya U.)
K. Tokunaga (Kyushu
U.)

Task 2
Irradiation
synergism

D. Sze(UCSD)

STC/Deputy (US)R. Doerner(UCSD)

1-2 Tritium
behavior inblanket systems

T. Terai (U. Tokyo)/
S. Fukada (Kyushu U.)
S. Konishi (Kyoto U.)

P. Sharpe(INL)/
P. Calderoni(INL)

1-3 Flow control
and thermofluid
modeling

T. Kunugi (Kyoto U.)/T. Yokomine(kyushu U.)

N. Morley (UCLA)/
K. Messadek(UCLA)

2-1 Irradiationtritium synergism

A.Kimura(Kyoto U.)

Y. Hatano (Toyama U.)/Y. Oya (Shizuoka U.)

R. Kurtz(PNNL)

M. Sokolov (ORNL)/
Y. Katoh (ORNL)
P. Calderoni (INL)

2-2 Joining andcoating integrity

A. Kimura (Kyoto U.)/N.
Hashimoto(Hokkaido U.)

T. Yamamoto(UCSB)/
M. Sokolov (ORNL)

2-3 Dynamic
deformation

A.Hasegawa(Tohoku U.)/
T. Hinoki (kyoto U.)

Y. Katoh (ORNL)

Common
Task
Systemintegration
modeling

MFE/IFE system
integration
modeling

Laboratory
Liaisons

ORNL :INL :IMR-Oarai (Tohoku) :IFE Liaisons

TC (US)

A.Sagara(NIFS)

A. Sagara (NIFS)/
H. Hashizume(Tohoku U) T.
Norimatsu (Osaka U.)

R. Nygren(SNL)

R. Stoller (ORNL)
P. Sharpe (INL)
T. Shikama (Tohoku U.)
K. Tanaka(Osaka U.)

Kodama(Osaka U.)
Yoneda(UTC)78

M. Tillack(UCSD)

R. Nygren (SNL)5.3

Administration

The administative structure of the JUPITER-II and TITAN projects are summarized in Tables 5-3
and 5-4, respectively. A Steering Committee Meeting is held annually for summarizing annual
achievements and planning activities for the following year.

References[ JUPITER-II project ]                               
K. Abe, A. Kohyama, S. Tanaka, C. Namba, T. Terai, T. Kunugi, T. Muroga, A. Hasegawa,
A. Sagara, S. Berk, S.J. Zinkle, D.K. Sze, D.A. Petti, M.A. Abdou, N.B. Morley, R.J. Kurtz,
L.L. Snead, N.M. Ghoniem, “Development of advanced blanket performance underirradiation and system integration through JUPITER-II project”, Fusion Engineering and
Design, 83 (2008) 842-849[ TITAN project ]                             T.
Muroga, D.K. Sze, K. Okuno, T. Terai, A. Kimura, R. Kurtz, A. Sagara, R. Nygren, Y. Ueda,
R. Doerner, P. Sharpe, T. Kunugi, N. Morley, Y. Hatano, M. Sokolov, T. Yamamoto, A.
Hasegawa, Y. Katoh, N. Ohno, K. Tokunaga, S. Konishi, S. Fukada, P. Calderoni, T.
Yokomine, K. Messadek, Y. Oya, N. Hashimoto, T. Hinoki, H. Hashizume, T. Norimatsu, T.
Shikama, R. Stoller, K.A. Tanaka, M. Tillack, “Midterm Summary of Japan-US Fusion
Cooperation Program TITAN”, 19th Topical Meeting on the Technology of Fusion
Energy, Nov. 7-11, 2010, Las Vegas, submitted.

79

Accomplishments
Highlights
5.45.4 Accomplishments
andandHighlights
5.4.1JUPITER-II
JUPITER-II
5.4.1
About
60 scientists
in15in15
Universities
fromfromJapanand about
50 scientists
in10in10
institutes
fromfrom
the US,
includingAbout
60 scientists
Universities
Japanand about
50 scientists
institutes
the US,
students,
joined joined
JUPITER-II
project.project.
Participants
are listed
the following
table. table.
including
students,
JUPITER-II
Participants
are inlistedin the following
Tableof participants
to JUPITER-II
project
Table
5-5 5-5
ListListof participants
to JUPITER-II
project

Task

Subtask

JapaneseParticipants

USParticipants

T. Terai, S. Tanaka, A. Suzuki, H.
Nishimura (U. Tokyo), M. Nishikawa, S.
Fukada, K. Katayama (Kyushu U.), K.
Okuno, Y. Oya (Shizuoka U.), Y.
Hatano, M. Hara (Toyama U.), A.
Sagara (NIFS)

D. A. Petti, G.R. Smolik, Michael F.
Simpson, John P. Sharpe, R.A. Anderl(INL), Dai-Kai Sze (UCSD)

T. Kunugi, Z. Kawara (Kyoto U.), T.
Yokomine, S. Ebara, H. Nakaharai(Kyushu U.), S. Satake (Tokyo U. of
Science), S. Toda, H. Hashizume, K.
Yuki (Tohoku U.)

M. A. Abdou, N. B. Morley, J. Takeuchi,
R. Miraghaie, S. Smolentsev, H. Huang,
Y. Tajima, , T. Sketchley, J. Burris(UCLA)

T. Muroga, T. Nagasaka, T. Tanaka(NIFS), T. Terai, A. Suzuki, Z. Yao, A.
Sawada(U. Tokyo), K. Abe, M. Satou, M.
Fujiwara (Tohoku U.)

B.A. Pint, M. Li, P. F. Tortorelli (ORNL),
A. Jankowski (LLNL)

1-2-B: V Alloy Capsule
Irradiation

T. Muroga, T. Nagasaka (NIFS), K.
Fukumoto (Fukui U.), H. Matsui, K.
Abe, M. Satou, H. Kurishita (TohokuU.), H. Watanabe, N. Yoshida, (Kyushu
U.) S. Ohnuki (Hokkaido U.)

R.J. Kurtz, D.S. Gelles, M.B. Toloczko(PNNL) D.T. Hoelzer, M. Li, S.J. Zinkle(ORNL), G..R. Odette, T. Yamamoto䠅(UCSB䠅

2-1: SiC Fundamental
Issues, Fabrication, andMaterial Supply

T. Hinoki, A. Kohyama, T. Nozawa, S.
䚸Kondo, H. Kishimoto䚸K. Shimoda(Kyoto U.) A. Hasegawa, (Tohoku
University), T. Shibayama (Hokkaido
U.)

Y.Katoh, L.L.Snead, B.A. Pint, S.J.
Zinkle, E. Lara-Curzio, H-T. Lin, R.A.
Lowden, G.C. McLaughlin (ORNL) C.H.
Henager, Jr., G.E. Youngblood, R.H.
Jones, C.A. Lewinsohn (PNNL)

2-2: SiC System
Themomechanics

A. Shimizu and T. Yokomine (Kyushu
Univ.), A. Hasegawa (Tohoku Univ.), A.
Kohyama, S. Konishi (Kyoto University)

A. Ying, M. Abdou, A. Abou-Sena, J. An
and T. Sketchley (UCLA), Y. Katoh(ORNL)

2-3: SiC Capsule
Irradiation

A.Hasegawa, S.Nogami (Tohoku U.),
T.Hinoki, A.Kohyama, T. Nozawa,
S.Kondou, K. Ozawa (Kyoto U.) ,T.Shibayama (Hokkaido U.)

Y.Katoh, L.L.Snead, B.A. Pint, S.J.
Zinkle, J.L. McDuffee (ORNL), C.H.
Henager, Jr., G.E. Youngblood (PNNL),
N.B. Morley (UCLA)

3-1: Design-based
Integration Modeling

A. Sagara, T. Tanaka (NIFS), S. Fukada,
M. Nishikawa (Kyushu U.), S. Tanaka,
T. Terai, A. Suzuki (U. Tokyo), S. Toda,
H. Hashizume, K. Yuki, S. Chiba(Tohoku U.), S. Satake (Tokyo U of
Science), T. Kunugi (Kyoto U.)

3-2: Material Systems
Modeling

N. Sekimura, T. Okita, H. Abe(U.Tokyo), K. Morishita, Y. Watanabe(Kyoto U.), M. Satou, N. Nita, H. Matsui(Tohoku University)

Task1:
1-1:
Self-Cooled FLiBe Cooled
Liquid
1-1-A: FLibe Handling
Blanket/Tritium Chemistry/Safety

1-1-B: FLibe Termofluid
Flow Simulation

1-2:
Li Cooled with 1-2-A: Coatings for MHD
V Alloy
Reduction
Structure

Task2:
High-Temperature GasCooled Blanket

Task3:
Blanket System Modeling80

N.M. Ghoniem, S. Sharafat, M.Z. Youssef(UCLA), Da-Kai Sze (UCSD)

B.D. Wirth (UC Berkeley), T. Diaz de la
Rubia, W.G. Wolfer (LLNL), N.M.
Ghoniem, S. Sharafat (UCLA), H.L.
Heinisch, F. Gao, R.J. Kurtz (PNNL),
G.R. Odette (UCSB), R.E. Stoller(ORNL)

Task 1-1-A㸸Flibe Handling/Tritium Chemistry
provide a controlled reaction between Be and HF in themolten salt phase. Each experiment started with the HF–
H2–He feed gas bubbled into the salt with the Be specimen
pulled out of the salt. Once the HF concentration in theefuent stabilized close to the expected level, the Be
specimen was inserted into the salt. After 10–60 min, theBe was lifted out of the salt and into its protective housing
while HF in the efuent was continually monitored fortimes ranging from several hours up to a few days. Once
the HF concentration in the efuent had again stabilized,
the next experiment was run by re-inserting the Be into thesalt for a different duration. The efuent HF concentration
as measured by the QMS dropped rapidly usually within amatter of minutes after the Be was initially inserted into thesalt. The slow increase of the efuent HF concentration
after the Be was removed is believed to be the result ofcontinued reaction of Be dissolved in the salt with HF
added by ongoing gas injection. Corrosion tests were also
performed with and without REDOX control for samples of
the advanced ferritic steel JLF-1. The dissolution rates ofFe and Cr were suppressed by dipping Be into Flibe.
However, their rates were increased when the Be rod waswithdrawn from Flibe. Exposures of up to 500 hours in the
non-flowing molten salt indicate a corrosion rate of
0.1μm/hr, with a Cr-rich oxide layer forming at the sample
interface. Corrosion is effectively halted during periods of
REDOX control using Be.

Category: JUPITER-II
Task: 1-1-A
Name: T. Terai / D. Petti
Affiliation: U. Tokyo / INEEL
Based on the key issues associated with the use ofFlibe (LiF and BeF2) as a coolant in a fusion blanket, theobjectives of our work are:1) to develop the capability to fabricate and purify Flibe at
the liter scale for use in the experiments;
2) to characterize tritium and deuterium behavior (e.g.,solubility and diffusivity) in REDOX(reduction andoxidation)-controlled and non-controlled Flibe;3) to characterize the magnitude and physio-chemical
forms of material mobilized during an accidental spillof Flibe and to develop safe handling practices;4) to develop a REDOX agent to control TF activities in
Flibe in a fusion blanket;
5) to demonstrate the effectiveness of the redox agent interms of structural material compatibility for fusionmaterials of interest using a simple dip specimens insmall scale pot type experiments.
(a) Flibe purication
The Flibe in the JUPITER-II was prepared fromreagent grade chemicals. Both the Be2F and LiF were listed
as 99.9% pure. Measurements of Be and Li in the nal
product ranged from 8.3 to 8.5 and 13.06 to 13.2 wt%,
respectively. Although these are lower than the theoreticalvalues of 9.04 and 14.14 wt%, Li to Be mole ratios of
2.01–2.06 are close to the targeted composition.

(d) Deuterium/tritium behavior
Deuterium permeation experiments were conductedin a cylindrically symmetric, dual probe permeation pot
setup. Several deuterium permeation experiments weremade with the system at temperatures of 600 and 650C andwith a deuterium pressure of around 9.0 x 104 Pa. TMAP-4
simulation calculations were used to evaluate the overall
deuterium permeation rates in the Flibe/Ni/D2 system.
These analyses showed that diffusion in Flibe was ratedetermining for our experimental conditions. Diffusivity of
T2 in Flibe which redox condition is sufficiently controlled
was determined. The activation energy of T2 in the redoxcontrolled Flibe was smaller than that of D2 in the nonredoxcontrolled Flibe.

(b) Flibe mobilization experiment
A key safety issue associated with Flibe is themobilization of vapors and aerosols from accidental
introduction of air, moist air, or steam to the molten salt.
Mobilization tests were performed with argon, air andmoist air using a classical transpiration apparatus designed
for vapor pressure determinations. Total measured
pressures for BeF2 and LiBeF3 are two to three times lower
than predicted values. The increasing contribution from the
Li species in the INEEL data is apparent at 700 and 800C.
Mass comparisons using probe interior ICP-AES
measurements and sample loss for the argon test series in
the nickel crucibles showed that about 22% of the material
was deposited in the probe. Mass ux calculation obtainedby adjusting ICP-AES measurements for the 22% factor
generally agreed within a factor of two of the mass based
determinations for individual tests.
(c) REDOX control and corrosion
A series of experiments was performed in which
HF was bubbled through Flibe with varying concentrationsof dissolved Be to investigate the viability of using Be as aredox agent in a molten Flibe (2LiF–BeF2) blanket. A
mixture of H2, He and HF gases was introduced into thetest reactor, while the efuent passed through a quadrupole
mass spectrometer (QMS) followed by an autotitrator. The
reactor, shown in more detail in Fig. 1, was designed toFig. 1 Reactor for measuring redox

81Task 1-1-B㸸FLibe Termofluid Flow Simulation
fluctuation decreases with increasing of the Hartmann
number. Thus, the application of the magnetic filed leads
the turbulent flow to the laminar flow: this phenomenon
usually calls a “Laminarization due to the Lorentz force.”
As for the heat transfer experiments, a part of thetest section of FLiHy loop was heated uniformly by heating
tape under the constant magnetic field up to 2.0 Tesla.
Forty T-type thermocouples with a diameter of 0.75 mm
were fixed with high thermal conductivity grease (15W/mK) in the holes of 1mm diameter at five axial stations
and eight angles from the horizontal magnetic field. The
depths of holes and the tube wall thickness were 4 mm and
5 mm respectively, i.e., the length from the inner tube
surface to measuring point was 1mm. Temperature of KOH
was monitored at both the inlet and the outlet of test section
using thermocouples. The bulk mixing temperature ofarbitrary cross section was estimated by the linear
interpolation from the inlet and the outlet temperature. The
radial temperature distribution of the fluid flow in the pipe
was measured by means of thermocouples tower (TCtower) which was consisted of the Inconel sheathed K-type
thermocouples with a diameter of 0.13mm arranged fromthe inner wall surface to the centre of the pipe. The 63%
response time of this thermocouple was 2 ms. The angle of
TC tower and magnetic field was set to 0 degree and 90
degrees. The Reynolds number based on bulk velocity andpipe diameter was set to 5000 and 20000 for Ha=0, 5, 10
and 15, and Pr=6 and 10. A non-dimensional mean
temperature distribution from the wall in case of Re=9000
indicated that the temperature inside the pipe increases incase of MHD flows, i.e., this is another evidence of thelaminarization of turbulent flow under the magnetic fields.
Influence of the transverse magnetic field on the heattransfer is also to suppress.

Category: JUPITER-II
Task: 1-1-B
Name: T. Kunugi / M. A. Abdou
Affiliation: Kyoto U. / UCLAA molten salt coolant, Flibe, has attracted attention
because high temperature stability and low magneto-hydrodynamics (MHD) pressure drop are special concerns.
However, there are some issues making Flibe-based
blanket design challenging. The main issues include low
thermal conductivity of Flibe, high kinematic viscosity andto need an additional neutron multiplier because of thelimitation of the tritium breeding capability of Flibe, andthe requirement of the structural material with temperature
range over 650C. The high viscosity and low thermal
conductivity put Flibe in the class of high Prandtl number
fluids. In order to obtain sufficiently large heat transfer
using high Prandtl number fluid coolant, high turbulence isrequired under a high magnetic field. Thus, it is important
to investigate the effect of magnetic fields on the flow andheat transfer characteristics of the high Prandtl number
fluids.
A pipe flow experimental facility called “FLiHy”(FLibe Hydrodynamics) was constructed at UCLA as
shown in Fig. 1. The experimental facility consisted of apipe flow loop with a transparent visualization section byusing a Particle Image Velocimetry (PIV) system. Purewater and 30% aqueous solution of potassium hydroxide(KOH hereafter) were used as a working fluid for NonMHD flow and MHD flow, respectively. The experimental
approaches include flow and heat transfer measurements
using a Flibe simulant fluid along with a direct numericalsimulation (DNS).
The flow facility utilizing water and low electricallyconducting fluid as a Flibe simulant was constructed, andturbulent flow field measurements using PIV and heattransfer measurements were carried out without magnetic
field using water as a working fluid to establish theexperimental techniques. The performance of this FLiHy
facility for the non-MHD flows in pipe was verified withhigh accuracy compared with the existing experimental
results and the DNS data.
As for MHD flow experiments, a magnet used forthe current experiments produces maximum 2.0 Tesla
magnetic fields in a narrow gap of the iron core at 3000 Aof applied electric current. The pipe flow test section wasplaced in the gap which was 1.4 m in the streamwise
direction, 25 cm in height, and 15 cm in width. The B field
has uniform distribution within 5% variation for 1.0 m inthe streamwise direction. The mean velocity measurements
were performed for five different Hartmann numbers: Ha =0, 5, 10, 15 and 20 (based on pipe radius). The mean
velocity profiles show that it becomes flatter as theHartmann number increases in the core region of the flow,
and that the near-wall velocity gradient increases withincreasing of the Hartmann number: this shows the typicalcharacteristics of the Hartmann flow. The streamwisevelocity fluctuation distribution in the radial direction for
Re=5300 showed that the intensity of the velocity

Measurement section

Laser

Flow direction
Tank
Light Sheet Probe
Electromagnet

FilterHeat exchanger
Flow meter

Fig. 1 Schematic drawing of FLiHy facility

82

Task 1-2㸸Lithium Cooled with V Alloy Structure
alloys using B-doping simulation techniques. Also carriedout were out-of pile thermal and environmental control
tests.
To examine the environmental effect onirradiation creep, pressurized creep tubes were enclosed in
Li-filled capsules and irradiated in HFIR to 3.7 dpa at 425
and 600C. The results were compared to similar specimens
enclosed in Na-filled capsules irradiated in JOYO. It was
found that the creep strain rate exhibited a linear
relationship with the effective stress up to 150MPa at 425C
as shown in Fig. 2. At 600C the creep strain was muchlarger than that at 425C. The activation energy ofirradiation creep was estimated to be 46kJ/molK. No
significant difference in irradiation creep behavior between
liquid sodium and liquid lithium environments wasobserved.
To understand the effect of stress state on thepropensity for localized deformation in vanadium alloys,
compression specimens, fabricated from Heat 832665 and
NIFS-1 heats of V-4Cr-4Ti, have been tested before andafter irradiation in the High Flux Isotope Reactor at 425°C
and 600°C to ~3.7 dpa. Irradiation at 425C to ~3.7 dpa
more than doubles the compressive yield strength of bothalloys at test temperatures of 25°C and 425°C. The increasein yield strength is due to production of unshearable defectclusters and precipitates.
The determination of ~1300ºC as the solvus
temperature for Ti(CON) precipitates in V-4Cr-4Ti resulted
in the establishment of a thermal-mechanical treatment(TMT) that redistributes the Ti solute atoms and O, N, andC interstitial atoms from an inhomogeneous distribution ofa low number density of coarse globular-shaped Ti(CON)
precipitates to a more homogeneous distribution of a highnumber density of nano-size plate-shaped Ti(CON)
precipitates. The modified TMT that produces the highnumber density of plate-shaped Ti(CON) precipitates andcold-work induced dislocations also improves the hightemperature strength properties of V-4Cr-4Ti.

Category: JUPITER-II
Task: 1-2
Name: T. Muroga / R.J. Kurtz
Affiliation: NIFS / PNNL(a) Task 1-2A : MHD coating for V/Li systems
The objective of this task is to develop coatings to
reduce the pressure drop associated with the magnetohydrodynamic (MHD) effect that were compatible with Li
at ~700°C. A strategy was laid out to evaluate bulk
ceramics in static Li compatibility tests followed bydevelopment of coatings and evaluations in static Li and inflowing Li with a temperature gradient. Also carried out inthis task were preliminary evaluation of irradiation effectsof the coating and fundamental investigation on theinterface structure and strength and mass-transfer in Valloy substrate/coating/Li system.
Based on the static immersion tests of candidate
bulk ceramics, the mass losses shown after 1000h
exposures in Li reflect the degree of dissolution. The
dissolution of CaO was observed. Calculations showed thatthe equilibrium solubility of Ca in Li increased
dramatically with temperature, which was consistent withthe high dissolution rates observed experimentally. Thus,
the task focused efforts on Y2O3 and Er2O3. Feasibility of
the coating with Y2O3 and Er2O3 on V-4Cr-4Ti wasdemonstrated by EB-PVD, Arc Source Plasma Deposition
and RF sputtering. Especially, Er2O3 fabricated with Arc
Source Plasma Deposition showed good corrosion
resistance. By deposition on a substrate at higher
temperature, high crystalline Er2O3 coating was produced,
which were shown to be stable in Li to 1000hr at 700°C.
Coating development focused on Y2O3 and Er2O3 and thenon these coatings with a vanadium overlayer. While massloss is one measure of performance, the principal figure of
merit is resistivity. Therefore, the resistivity of bulk
materials and coatings also was measured. For thecoatings, an in-situ test was developed to measure theresistivity of the coating in contact with Li. These tests,
along with static Li exposures, revealed that a single-layeroxide coating was not performing well and that multi-layer
coatings as shown in Fig. 1 showed superior performance.

Fe(V)~300nmEr2O 3~800nm(b) Task 1-2B : Vanadium Alloy Capsule Irradiation
In this task, irradiations of vanadium alloys and
MHD coating candidates in Li-filled capsules were carriedout in HFIR for the purpose of studying the irradiation
performance of structural components of V/Li blankets.
The experimental objectives are to a) investigate the effectof trace elements C, O, and N and minor alloying elements
Y, Al, Si on the properties of vanadium alloys irradiated at
425 and 600°C, b) study general aspects of deformation,
fracture, and irradiation creep at irradiation temperatures of
425 and 600°C, c) examine the irradiation performance of
weld joints of vanadium alloys mostly at 425°C, d) explore
the fundamental effects of neutron irradiation on bulk
ceramics relevant to MHD insulator coatings associatedwith Subtask 1-2-A, and e) perform a limited investigationof helium effects on mechanical properties of vanadium

V alloy
substrate

Fig. 1 Double layer of Er2O3/V and Er2O3/Fe on V alloy

Fig. 2 Creep strain vs. applied stress for US832665 and
NIFS-Heat 2 in HFIR Li capsule and Joyo Na-capsule83

Task 2㸸High-Temperature Gas-Cooled Blanket
notched beam (SENB) specimens. Based on that, J-integral
analysis of SENB fracture was selected as a standard test
method for post-irradiation examination of 18J specimens.

Category: JUPITER-II
Task: 2
Name: A. Hasegawa / R. H. Jones
Affiliation: Tohoku U. / PNNL(b) Subtask 2-2: SiC System Thermomechanics
The task 2-2 has broadened the understanding ofpebble bed material system thermomechanics and its
impact on the use of SiC/SiC structure in a helium-cooled
ceramic breeder blanket concept. The interface
conductance was found not to be a fixed value but varies
according to pebble bed thermomechanical state and design
associated mechanical boundary conditions. The thermal
stress induced by the differential thermal expansion
between the SiC structural clad and the ceramic breeder
pebble bed may crack the pebbles and cause the clad tobe separated away from the pebble bed. This can form a
gap at the interface and increase the breeder temperatureeven more. This makes a design that based on the ARIES-I
type concept with He coolant pass through coolant channel,
more challenging. The design based on the DREAM
concept, with He coolant pass in between pebble bed,
reduces the above concern, where heat generated inside thebreeder bed is removed by the forced convection (rather
than conduction as in the ARIES-I case.) However, a costeffective tritium extraction technology from high mass
helium flow rate is needed to make this concept attractive.

Materials design and fabrication, fundamental
properties evaluation, and micromechanical constitutive
modeling of materials behavior were studied in Subtask 2-1.
In aid of other subtasks, design, fabrication, and supply ofadequate SiC/SiC composites were also performed in
Subtask 2-1. Thermo mechanics, compatibility and heattransfer performance of the model gas blanket systems,
comprising SiC/SiC structure and ceramic breeder pebbles
were studied in Subtask 2-2. Based on the material
development and the thermo-mechanical analysis, radiation
behavior of the advanced SiC/SiC composites and elementsof solid breeding blanket systems in high temperatureenvironment were studies in Subtask 2-3.
(a) Subtask 2-1: SiC/SiC Fundamentals and Material
Processing
Extensive R&D efforts for development andcharacterization of advanced SiC/SiC composites for fusion
have been successfully carried out in Task 2-1. The FCVI
process using high purity SiC fibers was optimized anddensity, mechanical properties and uniformity were
improved significantly. Figure 1 shows multilayer
fiber/matrix interphase of reduced C and SiC and fracturesurface of the composites. Complicated fracture at thefiber/matrix interphase increased ultimate tensile strength.
Advanced small specimen test technologies and procedures
for mechanical properties of SiC/SiC were developed.
Joining and hermetic sealing using of NITE SiC/SiC and
CVI / NITE hybrid process has been explored. The robust
joining technique using NITE joint was successfully
developed and evaluated. The optimized composite
samples were produced and supplied to irradiation
experiments. Refractory coating technique for SiC and
SiC/SiC composites was also developed by infraredtransient liquid phase processing. The tungsten armoredsilicon carbide samples proved uniform, strong, andcapable of withstanding thermal fatigue testing. Guidance
was provided for selection of appropriate materials for the
pebble-bed thermo-mechanics experiments.
Anisotropyof
SiC/SiC
composites
wascharacterized by transthickness tensile test, diametralcompression test and shear test using double-notched
specimens in addition to basic tensile test. The diametralcompression experiment for SiC/SiC composites was
newly developed and size effect was also evaluated.
Progress has been achieved in the areas of fracture
toughness evaluation and interfacial shear properties
characterization for advanced SiC/SiC composites, andchemical compatibility of SiC in dual-cooled blankets. The
fracture behavior of advanced SiC fiber composites withchemically vapor-infiltrated (CVI) and nano-infiltrationand transient eutectic-phase (NITE) SiC matrices weresuccessfully evaluated by bend testing of single edge(b) Subtask 2-3: SiC Capsule Irradiation
In order to demonstrate feasibility of highefficiency gas cooling blanket system using advanced
SiC/SiC composites based on new material development
strategy and irradiation resistance of the material system
was examined. Evaluation of radiation resistance of SiC
and advanced SiC/SiC developed and fabricated JUPITERII program were performed using HFIR irradiation ( rabbit
capsule and HFIR-18J RB* capsule irradiation). Additional
irradiation data of the advanced SiC/SiC and SiC was alsocollected by alternative irradiation facilitates such as JMTR,JOYO and charged particle irradiation facilities. Radiation
resistance of advanced SiC/SiC composite wasdemonstrated. Guideline of radiation resistance of SiC/SiC
composites was confirmed. Engineering data of advanced
SiC/SiC composites at high irradiation temperature wascollected. The data shows feasibility of the hightemperature gas cooling system with SiC/SiC composites.

(b)

(a)

2Pm

5Pm

Fig. 1 A SEM image of (a) multilayer (C/SiC) fiber/matrix
interphase and (b) fracture surface of the composites

84

Task 3㸸Blanket System Modelingissues, including primary radiation damage formation,
extended defect formation and evolution, dislocation-defectinteraction, dislocation dynamics, developing constitutive
relationships for irradiated materials, and predictions ofengineering properties of materials needed for component
design. For this purpose, wide variety of evaluation
techniques should be used, because a solid material has
essentially a hierarchical structure from atoms tocontinuum bodies, and a radiation damage process isessentially a multi-time, -length and -energy scale
phenomenon.
Morishita et al. have investigated the nucleationand growth process of helium bubbles in Fe. They
employed molecular dynamics and molecular statics
calculation techniques as well as continuum theory to
determine the formation energy of helium bubbles.
Furthermore, they introduced these results as input
parameters in kinetic Monte-Carlo simulations, thus
enabling us to study the nucleation kinetics of helium
bubbles as a function of temperature and point defectconcentrations in an Fe matrix. This work was performedin collaboration with LLNL, PNNL, UC Berkeley and
UCLA.
Abe et al. performed molecular dynamics
calculations to investigate dynamical interactions between
an SFT and a dislocation, and they estimated the effects of
the interaction on radiation-induced hardening. Also, they
investigated the migration behavior of a crowdion bundle
using a molecular dynamics technique. They compared thecalculation results with in situ TEM observations. This
work was performed in collaboration with ORNL.
Fundamental understanding of metal/ceramics
bonding will provide useful guideline to develop a robust
coating technique. Satou et al. performed ab-initio
calculations to investigate bonding states between
vanadium and coated CaO. This work was done incollaboration with UCLA and CSUN.
Sharafat et al. investigated the transport of heliumin irradiated materials driven by spatially dependent fields,such as temperature and stress gradients. To this end
modeling of helium transport through finite geometries
thus requires a spatially dependent helium transport model.
A spatially resolved rate-theory based helium bubble
evolution code was developed at UCLA, called HEROS(Helium Bubble Evolution and ResOlution Code).

Category: JUPITER-II
Task: 3
Name: A. Sagara / N. Ghoniem
Affiliation: NIFS / UCLA(a) Subtask 3-1: Design-based Integration Modeling
The main purpose of this task is to develop
integrated engineering models of blanket systems based on
fusion reactor designs. The constraints imposed by one areaof research must be considered in solving problems in
another area. Integration has been accomplished in theareas of tritium transport and permeation, thermofluids,
materials, and neutronics. For this purpose, it is essential
to optimize the blanket system not as a single component
but as an integrated system device under the boundary
conditions of burning core plasmas and out-vessel
environments. Therefore, collaboration works withconnecting each task are basically quite important.
Fukada et al. have revealed that, for the FFHR
blanket system, tritium permeation windows in a realisticscale are usable for tritium disengager systems. It is foundthat the diffusion process of tritium in Flibe or the surface
process at the boundary is the critical rate limiting process
to be investigated. From the safety point of view, they haveproposed that a small amount of Flibe or He gas flow in the
double tube can act as an effective permeation barriers to
reduce the tritium leakage rate below 10 Ci/day.
Sagara et al. have newly proposed the STB(Spectral-shifter and Tritium breeder Blanket) for
replacement-free blankets in the reactor life of 30 years in
FFHR. For this STB, they have evaluated the first wallcondition for FFHR, and have proposed enhancement ofFlibe cooling capability on one-side heating over 1MW/m2.
Hashizume et al. have investigated flow structuresin sphere-packed pipes to enhance heat-transfer efficiency
in the TNT (Tohoku-NIFS Thermofluid) loop experiments
using HTS (Heat Transfer Salt, Tm= 142°C). Same
performance as turbulent flow has been obtained at oneorder lower flow rate. This is a big advantage for reducing
MHD effects and the pumping power.
Tanaka et al. have started a new challenge toconstruct an interface code between the Monte-Carloneutron transport code MCNP-4C and a complicatedblanket design such as in helical systems in order to enable
us to frequently modify blanket designs and quickly checkneutronics performance. The examples are shown in Fig. 1.
Using this easy-feedback code system, both of the Flibecooled reduced-activation ferritic steel (RAFS) and Li/Valloy blanket systems have been optimized in the feasibilityof tritium breeding ratio higher than 1.0 and nuclear
shielding in the FFHR2m helical design.
(b) Subtask 3-2: Materials Modeling
The goal of this task at the beginning of the
JUPITER-II project was to establish the methodology of“Multiscale Modeling of Mechanical Deformation (M3D)”
for contributions to the research and development of fusionmaterials, which may cover a broad range of fundamental

FIG. 8. Top view of calculated neutron wallload distribution. (72 o of the torus)

Fig. 1 Example of 3-D geometry data with MCNP (~3,000
cells) and helical neutron wall loading85

5.4.25.4.2TITAN
TITAN
About
70 scientists
in 20inUniversities
fromfrom
JapanJapanand about
50 scientists
in 10ininstitutes
fromfrom
the US,
About
70 scientists
20 Universities
and about
50 scientists
10 institutes
the including
US, including
students,
joinedTITAN
project.
Participants
are listed
in theinfollowing
table.table.
students,
joinedTITAN
project.
Participants
are listed
the following
Table 5-6 List of participants to TITAN project
Task

Subtask

Japanese Participants

Task 1
Transport
phenomena

1-1 Tritium andmass transfer infirst wall

Y. Ueda䠄Osaka䠄 U.䠅, K. 䠅
Tokunaga, T. Ohtsuka (KyushuU.), N. Ohno, S. Kajita (NagoyaU.), M. Miyamoto (Shimane U.),M. Nagata, Y.Kikuchi (Hyogo
Pref. U.)

R.P.Doerner, D. Nishijima, M.
Baldwin (UCSD), P. Sharpe, M.
Shimada (INL)

1-2 Tritium
behavior inblanket systems

T. Terai (U. Tokyo), S. Fukada,K. Katayama, Y. Edao (KyushuU.), S. Konishi, Y. Yamamoto, T.
Kamei, K. Noborio (Kyoto U.)

P. Sharpe, P. Calderoni, M.
Shimada (INL), D.-K. Sze (UCSD)

1-3 Flow control
and thermofluid
modeling

T. Kunugi, Z. Kawara, Y. Ueki
(Kyoto U.), T. Yokomine, S.
Fukada (Kyushu U.), S. Satake,
K. Yuki (Tokyo U. Science), H.
Hashizume, S. Ebara (TohokuU.), M. Kondo (NIFS)

N. Morley, K. Messadek, S.
Smolentsev, A. Ying, M. Dagher, J.
Takeuchi, M.Abdou (UCLA), R.
Munipalli (Hypercomp), C. Wong(GA), P. Calderoni (INL), D.-K. Sze(UCSD)

2-1 Irradiationtritium synergism

Y. Hatano, M. Hara, S. Akamaru,
K. Zhang, A. Nozaki (ToyamaU.), Y. Oya, M. Kobayashi(Shizuoka U.), T. Oda (U. Tokyo),
K. Satoh (Kyoto U.), H.
Kurishita, K. Nagai, K. Toyama(Tohoku U.)

M. Sokolov, Y. Katoh (ORNL), P.
Calderoni(INL), R. Stoller (ORNL),
T. Yamamoto (UCSB), P. Sharpe,
M. Shimada, S.Shultz(INL), R.
Kolasinski (SNL)

2-2 Joining andcoating integrity

A. Kimura, R. Kasada,
K.Yabuuchi (Kyoto U.), S. Ukai,
S. Ohnuki, N. Hashimoto(Hokkaido U.), A. Hasegawa, H.
Kurishita (Tohoku U.), H.
Watanabe (Kyushu U.), T.
Nagasaka (NIFS)

Roger Stoller䚸Michel䚸 Sokolov䚸
Yutai Katoh(ORNL)䚸Takuya
䚸Yamamoto(UCSB)䚸Rick䚸
Kurtz(PNNL)

2-3 Dynamic
deformation

A. Hasegawa, T. Shikama, S.
Nogami, H. Katsui (Tohoku U.),
T. Hinoki, S. Kondoh (Kyoto U.),
T. Shibayama (Hokkaido U.),Y.B. Choi (Hiroshima U.)

Y.Katoh, L.L.Snead, E.Byun,
K.Ozawa, R.Stoller䠄ORNL),
䠄C.Henager, R.Kurtz (PNNL),
S.Sharafat, N.Morley (UCLA)

MFE/IFE system
integration
modeling

A. Sagara (NIFS), T. Norimatsu(Osaka U.), H. Hashizume(Tohoku U.), K. Morishita, S.
Konishi, T. Kunugi, A. Kimura(Kyoto U.), T. Yokominem S.
Fukada (Kyushu U.),, T. Terai(U. Tokyo)

R.Nygren(SNL), R.Causey,
P.Sharpe (INL), D. Sze,
R.Raffray(UCSD), M.Abdou,
N.Morley, S.Smolentsev, A.Ying,
K.Messadek, N.Ghoniem,
S.Sharafat(UCLA)

Task 2
Irradiation
synergism

Common
Task
Systemintegration
modeling

86

US Participants䚸Task 1-1 : Tritium and mass transfer in first walls
Category : TITAN
Task : 1-1
Name: Yoshio Ueda, R. Doerner
Affiliation: Osaka University, University of California,
San Diego(2) Tritium
distributionintungsten,
F82H(Ferritic/martensitic low activation steel), and tungsten
coated F82H (VPS coating) exposed to TPE T/D
plasmas were measured by these methods. For tungsten
samples, tritium distribution is well described by simple
diffusion of T and D, while for F82H T distribution was
not simply understood by a diffusion equation with asingle diffusion coefficient and a plasma ion source
term. More experimental data are necessary to draw
some conclusions. For tungsten coated F82H, it was
clearly shown that the W coating layer greatly reduced
T diffusion into the F82H substrate material.

1. Background and Purpose
It is of great importance to understand tritium behavior infusion reactors in terms of safety and fuel economics. In
fusion reactors, edge plasma environment is very
complicated. Several ion species such as fuel ions (D, T),
fusion reactant (He), wall materials (Be, W, C for ITER 1 st
set of divertor), and edge cooling gas (Ne, N, Ar). In
addition, neutron irradiation would affect material
degradation due to radiation damage and transmutation.
These effects, especially synergistic one, are still underintensive investigation and are not known very well. In
addition, first walls of blankets will be coated with armor
materials (probably tungsten), but it is not well known how
this armor layer affect tritium retention and diffusion. In
Task 1-1 of TITAN, the purpose is to clarify tritium andmass transfer in the first walls of blankets by using tritium
plasma, Be and He seeded plasma, and pulsed laser system.

Results from PISCES(1) D/He (He:20%) mixed plasma exposure to puretungsten was made at 573 K. By He addition, D retention
was decreased by two orders of magnitude and blistering
seen for pure D exposure was suppressed. According to
TEM observation, thickness of He nano bubble layers was
20-30 nm, see Fig. 1, this layer could have some functions
to reduce D influx and increase D release, leading tosignificant reduction of D retention.

2. Research plan
In Task 1-1, the following subjects are studied.
(1) To investigate tritium retention and diffusion behavior intungsten and tungsten coated reduced activation materials(F82H, Vanadium alloy)(2) To investigate production processes of material mixing
layers and D retention by Be/He/D mixed plasma irradiation
to tungsten under high temperature (>1100 K) and low
temperature (~600 K) conditions.
(3) To investigate erosion of Be/W mixed materials undersimultaneous irradiation of high density plasma and pulsed
laser.

Fig. 1 Cross sectional view of He nano bubble layer
exposed to D/He mixed plasma at 573 K.
(2) Pure He plasma exposure to various W (SCR, stressrelieved, W-Re alloy, fine grained W) at ~1100 K always
showed nano-structure (often called “fuzz”).
(3) Simultaneous plasma and pulsed laser irradiations tosolid Be and Be coated W were performed. Structure ofablation plume formed by Be atoms (clusters) and BeD
molecules was observed.

3. Experimental facilities
Tritium Plasma Experiment (TPE) in INL : High density
tritium plasma simulator TPE is used to expose specimens
with T/D mixed plasma (T/D = 0.1~0.5%). Then specimens
are cut in a dry system and 2D tritium distribution ismeasured by Imaging Plate (IP).
Plasma Interactive Surface Component Experimental
Station (PISCES) in UCSD : Be/He/D mixed high density
plasma is exposed to tungsten. Then D retention
mesurement by thermal desorption spectroscopy (TDS) andobservation of microstructure (He bubbles, etc.) bytransmission electron microscope (TEM) are made.
Ablation of Be/W mixed layer by pulsed laser irradiation are
made.

Domestic activity(1) Be/W mixed layer formation processes are simulated by
the EDDY code.
(2) Effects of pulse plasma irradiation to tungsten preexposed to D/He at 573 K and 1100 K were examined.
5. Future directions
Task 1-1 activity came to halt after first half of 6 years
period of TITAN because of budget reduction. But
collaboration with UCSD and INL will continue based on
TITAN achievements. In addition, domestic research
activity will be activated more by the impact of TITAN
collaboration.

4. Principal achievement in first half of TITAN
Results from TPE(1) A new method to study tritium distribution in materials
exposed to T plasmas with a dry cutting and IP
technique.

87

Task 1-2: Tritium behavior in blanket systems

Main achievements
The initial focus of the experiments was the measurementof hydrogen solubility in LLE in a static configuration.
The figure below summarizes the results first obtained withhydrogen at input pressure above the liquid surface ranging
from 10 Pa to 100 kPa and LLE temperature ranging
between 300 C and 650 C. The dotted lines are theexponential fits proposed by F. Reiter and A. Aiello andused here to summarize the extremes of the wide range ofresults reported in the literature. However, the initialtechnical approach was based on a set of implicit
assumptions which have been undermined by the first 3
years experimental results, resulting in a more complex
matrix of parametric evaluation of materials, test
procedures and system configurations required toaccurately define the solubility. As a result system
optimization for tritium testing is still ongoing.

Category : TITAN
Task : 1-2
Name: T. Terai, S. Konishi, S. Fukada, P. Sharpe, P.
Calderoni
Affiliation: Tokyo University, Kyoto University, Kyushu
University, Idaho National Laboratory
Background and purpose
In a fusion energy system tritium is generated by neutron
capture in the blanket’s breeder material, extracted and recirculated as fuel in the plasma. When the breeder isdesigned to operate in the liquid phase, the interaction oftritium with the lithium bearing material is one of the mostimportant physical processes in determining the feasibility
and the attractiveness of the system because it isfundamentally linked with all aspects of plant operation,from fueling (tritium breeding ratio, tritium availability,etc) to power extraction (heat transfer capability, heat cycle
efficiency, etc) to safety (tritium inventory, tritium release,etc). Since the blanket operates in steady-state conditions,the accurate determination of the tritium solubility, definedas the function linking the concentration of dissolved
tritium with its corresponding partial pressure atequilibrium over the liquid surface, is a fundamental design
data need for all systems (magnetic or inertial confinement,
hybrid systems, etc) based on liquid breeders. The othermain transport properties, the diffusion constant and themass transport coefficient at liquid and structures interfaces,play a major role in the selection and optimization of thetritium extraction and coolant purification system (in dual
function blankets the two systems are acting on different
fluids).
Another aspect related to tritium transport in blanket
systems considered in this task is the evaluation of tritium
permeation barriers, which may play a fundamental role inmaintaining the tritium emission to the environment within
the regulatory limits in a fusion energy system. Although
the fabrication of such materials is not included in the Task
scope, samples may become available from recent
developments both in Japan and the US and could be tested
with tritium within TITAN activities.

Fig. 1 Temperature dependence of hydrogen solubility in
LLE (initial results)
Pre-conceptual design analysis of a forced convection
experiment to investigate tritium extraction from leadlithium eutectic based on the vacuum permeator concept
have also been carried out. They resulted in the definitionof the main components based on a single leg loop,
although further design development and construction is
not currently foreseen.

Test plan
1. Measure hydrogen isotopes solubility in lead-lithium
eutectic at blanket conditions
2. Tritium permeation in structural materials andpermeation barriers at very low concentrations
3. Investigate tritium extraction from lead-lithium eutectic
at blanket conditions
4. Modeling and system design for tritium extraction fromfusion blankets

Future directions
Tritium solubility tests will start in FY10 in parallel with
continued evaluation with hydrogen in a second bench-top
experimental system that will later be modified toinvestigate other transport properties (diffusivity, masstransport coefficient). Test of tritium permeation barriers isforeseen in the last 2 years of the collaboration.

Facilities
Several experiments including a dedicated tritium glove
box at the Safety and Tritium Applied Research facility,
Idaho National Laboratory.

88
Task1-3: Flow control and thermofluid modelingCategory : TITAN
Task : 1-3
Name: Tomoaki Kunugi, Takehiko Yokomine, Neil
Morley, Karim Messadek
Affiliation: Kyoto University, Kyushu University,
University of California Los Angeles (UCLA)

the HT-UDV [2] was obtained and a tracer particle for PbLi
flow was investigated. Interfacial phenomenon related to the
PbLi wettability may affect the MHD flows. This task has
made the quantitative evaluations of the interfacial effects
by measuring the contact angles of a PbLi droplet on asilicon carbide (SiC) surface, and also measuring anelectrical contact resistivity at a SiC-PbLi interface.
MHD modeling and numerical simulation
In order to establish the MHD flow control manners,
some MHD models and numerical simulations have been
conducting and the MHD turbulent effects on the heattransfer has been studying. A mixed convection which
consists of both a forced convection driven by pump and anatural convection due to the buoyancy under the strong
magnetic field is one of the key issues for the blanket
designs. This task has developed the turbulent model for a
MHD quasi two-dimensional (MHD-Q2D) flow, and also
numerically simulated the MHD-Q2D flows based on thismodel, so that the detailed understandings on the complex
thermofluid where strong magnetic field and the buoyancy
force interact (Fig. 2) have been obtained [3]A liquid metal (LM) flow in a fusion blanket interacts
with a plasma-confining magnetic field, and eventually aflow structures is strongly affected by a MHD (magnetohydrodynamics) effect. Especially, LM flows under thestrong magnetic field including the flow instabilities and theflow distribution in a coolant channel such as a manifold
may determine the heat removal, the hot spots, thecorrosion and the tritium transport. Therefore, theunderstanding of MHD themofluid behavior and the flow
control are the key issues for fusion blanket research anddevelopment. This task has been studying characteristics ofthe thermofluid under the strong magnetic field andmodeling the MHD phenomena. This task conducts someMHD experiments using the MTOR (Magneto-Thermofluid
Omnibus Research) facility at UCLA, which is able to makea uniform magnetic field of maximum 2T in a rectangular
gap of 15 cm in width and 1m in length.
LM flow distribution tests under strong magnetic field
Flow distribution of liquid metal in the coolant
manifold was studied, which consists of three parallel
channels under strong magnetic field with the electricallyinsulating walls. The working fluid was mercury, and theelectrical potential probes were used to measure the flow
rates in each channel. As results, a uniform distribution wasachieved in the case of the ratio of a magnetic force (Ha)and an inertia force (Re): N = Ha2/Re > 90 (Fig. 1) [1].

B

D

A

C
Temperature, C

Laminar flow
Turbulent flow

Laminar flow
Turbulent flow

Radial Distance(Rer, Rec, Rel) x 104

Ha=421

Ha=1218

Ha=547

Ha=687

Ha=1503

Ha=2032

Re x 104

Fig. 2. A: MHD buoyancy flow B: MHD Q2D flow
C: MHD turbulent effect on temp. profile
D: M-shaped velocity profile

Ha=960This task focuses on PbLi flows under strong magnetic
field in later half of TITAN project. At present a PbLi loop
at UCLA is being constructed, and the non-MHD/MHD
flow measurements with the HT-UDV system installed on
the PbLi loop will be conducted. Moreover in the latter halfof TITAN project, this task plans to carry out anexperimental study on the main techniques mitigating the
MHD pressure drop, e.g. a flow channel insert (FCI) and anelectrically insulation coating techniques.
The goal of this task is that MHD thermofluid models
based on both experiments and numerical simulation are
established for designing the fusion LM blanket.
1) Messadek, K. et al., Magnetohydrodynamics, 45 (2009)
233-238.
2) Ueki, Y. et al., Fusion Sci. & Tech., 56 (2009) 846-850
3) Smolentsev. S. et al., Fusion Eng. & Des., 83 (2008),
771-783

Ha=2429

NN>90
> 90

Fig. 1. The LM flow distribution under B-field
Development of PbLi flow diagnostic and interfacial effects
A lead-lithium eutectic alloy (PbLi) is chosen as aworking fluid in this task because the PbLi is one of thecandidates of LM coolants for fusion blanket designs. In
order to grasp the PbLi flow field, we have been developinga High-Temperature Ultrasonic Doppler Velocimetry (HTUDV). To do this, PbLi acoustic properties necessary for89Task 2-1 : Irradiation-tritium synergism
Category : TITAN
Task : 2-1
Name: Yuji Hatano, Yasuhisa Oya, Mikhail Sokolov,
Yutai Katoh, Pattrick Calderoni
Affiliation: University of Toyama, Shizuoka
University, Oak Ridge National Laboratory (ORNL),
Idaho National Laboratory (INL)(2) Measurement of Thermal Desorption Spectrum ofDeuterium from Low-Dose Neutron-Irradiated W
The W sample irradiated at 50 oC for 0.025 dpa wasshipped INL and exposed to deuterium plasma by linear
plasma machine TPE. The samples used in the present study
are significantly small and thin in comparison with thestandard size for TPE (1 inch diameter and ca. 1mm
thickness). Hence, a new sample holder specially designed
for the small samples with thermocouple mounted on
precise linear motion feedthrough was fabricated. The
surfaces of neutron-irradiated W samples were covered byblack contaminant, although the samples were kept in sealed
Mo envelopes during irradiation. One of W samples was
exposed to deuterium plasma by TPE at ca. 200 oC and fluxof 5.0×1021 D m-2s-1 for 2.0 h (fluence 3.6×1025 D m-2).
After exposure to deuterium plasma, the black contaminant
completely disappeared from the exposed surface, indicating
this black matter is the layer of W oxides. The cause ofoxide formation was considered to be a leak in Mo
envelopes resulting in reaction between samples and coolant
water. Although the contaminant remained on side andbackside, preliminary thermal desorption spectrum wasmeasured as shown in Fig. 1. Characteristic points ofspectrum from neutron-irradiated samples are: (1) burst-likedesorption observed in the low temperature region (䠘100oC), and (2) continuation of desorption in the temperature
range above 500 oC. The burst-like desorption was ascribedto deuterium release from oxide layers on the side andbackside. The desorption in the high temperature region
was attributed to the trapping effects by defects created byneutron irradiation. It should be emphasized that such clear
effects of neutron irradiation was observed at irradiationdose as low as 0.025 dpa. The measurement will be
repeated after removal of oxide layers from all surfaces.
Measurements of deuterium depth profiles with nuclear
reaction analysis are currently under preparation. Behaviorof hydrogen isotopes including tritium in high dose samples
will also be examined in the near future.

18

Desorption flux / 10 D m s-2 -1(1) Determination of Irradiation Matrix
From the viewpoints of neutron-induced activation,
small samples are preferable. On the other hand, accuracy ofretention and desorption measurements could be poor if
samples are too small. In order to optimize the sample size,radioactivity after neutron irradiation was evaluated by
FISPACT-2001 code in NIFS, and the accuracy ofmeasurements was assessed with expected hydrogenisotope retention. Finally, the sample size was determined to
be I 6 mm x 0.2 mm. Small samples (I 3 mm x 0.2 mm)
were also prepared for microstructure examination.
Conditions of neutron irradiation were determinedby taking account of expected wall temperature and neutron
dose in fusion reactors, development of microstructure andproject schedule. Irradiation temperature was decided to be
50 oC (quick start of irradiation due to simple capsuledesign), 300 oC (close to wall temperature of existing fusion
machines and ITER), and 650 oC (close to expected wall
temperature in DEMO). In W, only interstitial atoms
migrate at 50 and 300 oC, while vacancy diffusion and void
growth take place at 650 oC. Similar difference inmicrostructure is obtained for Ni by the irradiation at 50
and 300 oC.The duration of irradiation was determined tobe ca. 1 day, 1 month and 1 year (W only). Tungsten
receives irradiation dose of 0.025, 0.3 and 2.4 dpa(displacement per atom), and that for Ni is 0.1 and 1.2 dpa.
Irradiation at 50 and 300 oC for ca. 1 day and
1 month has been completed. The extent of activation afterca. 1 day irradiation at 50 oC agreed well with the abovementioned evaluation.

㻌

2.5
XQLUUDGLDWHGXQLUUDGLDWHGXQLUUDGLDWHGXQLUUDGLDWHG
GSD

2.0
1.5

o

10 C/min㻌

Understanding of tritium behavior (diffusion, trapping,desorption, etc.) in neutron-irradiated materials is
indispensable for evaluation of tritium balance in fusion
reactors. Tungsten (W) is currently recognized as candidateof plasma facing material because of its low tritium
solubility. Recent ion irradiation experiments, however,show that the radiation defects in W such as vacancies andvoids act as strong trapping sites against hydrogen isotopes.
Hence, the tritium retention in W may significantly increase
with neutron irradiation. The objective of this work is tounderstand the effects of neutron irradiation on tritium
behavior in W. Disk-type samples of pure W are irradiatedin HFIR, ORNL and retention and desorption of hydrogenisotopes including tritium are examined in STAR facility,
INL. Nickel is also examined as reference material.
Accomplishments in the first three years are described here.

1.0
0.5
0.0

0

100 200 300 400 500 600 700 800 900oTemperature / C
Fig. 1. Preliminary data on deuterium desorption from W
sample irradiated by neutron at 50 oC for 0.025 dpa. Spectrafrom unirradiated tungsten samples are also shown.

90

Task 2-2 : Joining and coating integrity
Category: TITAN
Task : 2-2
Name: Akihiko Kimura1, Naoyuki Hashimoto2,
Takuya Yamamoto3, Michel Sokolov4,
Affiliation:1Kyoto University, 2Hokkaido University,
3
UCSB, 4ORNL,
There are many issues to be solved for practicalconstruction of DEMO blanket, although the basic blanket
fabrication technologies for ITER test blanket module
made of reduced activation ferritic steels have been wellprogressing so far. Among the technologies,
joining/coating technology is inevitable for assembling
blanket in which the weld line is expected to be 500 m per
single body of blanket module. Therefore, it is consideredthat the lifetime of the blanket will be controlled by
performance of weld bond.
The objective of this sub-task is to develop thejoining and coating technology of advanced structural
materials for DEMO blanket and to evaluate theperformance of the joint and coating under irradiation.
The materials used were nano-sized oxide
dispersion strengthened (ODS) steels, vanadium alloys and
SiC composites. Since the ODS steels can be
simultaneously used with reduced activation ferritic steels(RAFS) without any significant design modifications,
ODSS/RAFS joint as well as ODSS/ODSS joint fabrication
technology development were targeted. The maximum
usage temperature of the ODSS is considered to be 150qC
higher than RAFS, which can contribute to elevate thermal
efficiency of the reactor. However, melting during welding
changes the morphology of the dispersion of nano-oxide
particles and degrades material performance, the otherjoining method than welding is necessary for ODSS. In thissub-task, friction staring welding (FSW) and solid state
diffusion bonding (SSDB) method was applied to the
ODSS (16Cr-4Al-2W-0.35Y2O3), and the joints were
irradiated in HFIR to be evaluated their performance underirradiation.
FSW was performed for an ODS steel with high
Cr concentration at a rotating speed of 800 rpm with a linescanning speed of 50 mm/min. The FSW treatment resulted
in a growth of the grains, and consequently, a remarkablereduction of the strength at RT. However, the reduction ofstrength at elevated temperatures was so small that the
FSW is adequate for the application of ODSS to practicalblanket fabrication..
SSDB was carried out at 1200qC at 25MPa for 1
ht with and without insert material. Since the melting
temperature of the insert material was lower than 1200qC,
insert material is melted and the method is often called asliquid state diffusion bonding (LSDB). Tensile strength ofboth the SSDB and LSDB was not degraded by thebonding treatment. The elongation of LSDB was reduced
to about a half of the material. However, the elongation of
SSDB was not reduced at all, indicating the joining method
is very suitable to ODS steels.

Fig.1㸸Schematic diagram of FSW method and a FSW
treated ODS steel.


Fig.2㸸Tensile stress and elongation of the ODS steel
with and without joining.

W-coating technology is inevitable for fabricationof diverter and first wall towards realization of fusionenergy. The most difficulty of W in application is due tobrittleness of W that was not plastically deformed at RT.
Plasma facing material, which suffer a cyclic high heatloading, has been required to be refractory material andresistant to high thermal fatigue. Furthermore, thesustaining structure of diverter and first wall should contact
to the coating tightly.
In this work, SSDB of W-ODSS was done at
1240qC with and without insert material (Fe-3B-5Si). The
strength of joint between W/ODSS was evaluated bymeans of torsion tests, and a rather high value of 300 MPa
was attained for the SSDB joint. A vacuum plasma splay(VPS) method was also attempted for W-coating on ODSS.
It was confirmed that the fabricated W-coat on ODSS
withstood a cyclic heat load at 4.8 MW/m2 to 16 cycles.
As a summary, the following accomplishments
were obtained in this sub-task:
1) ODSS/ODSS joint technique was developed.
2) The joint strength of 300 MPa was obtained for LSDB
joint of W/ODSS.
3) Non-damaged W-coat was fabricated on ODSS in termsof cyclic heat loading test at 4.8 MW/m2 to 16 cycles.

91

Task 2-3 : Dynamic deformation
NITE processed SiC matrix. The dimensions of the BSR
creep specimens are 40 mm (l) x 1 mm (w) x varied
thickness. The thickness was varied to allow determinationof the effect of stress magnitude. Typical initial flexuralstresses for the specimen thicknesses 0.05, 0.1, and 0.15mm are ~100, ~200, and ~300 MPa, respectively. The
neutron irradiation experiments were performed using
hydraulic and fixed rabbit facilities of the High Flux Isotope
Reactor (ORNL). Target irradiation temperatures andfluence in the Phase-I were 300, 500, 800, and 1200ºC in
the irradiation level from 0.01 to 1dpa[2].

Category : TITAN
Task : 2-3
Name: Akira Hasegawa (1), Tatsuya Hinoki(2), Yutai
Katoh(3)Affiliation:(1) Tohoku University, (2) Kyoto University, (3)Oak Ridge National Laboratories
1. Background and objectives
Irradiation creep is an important irradiation effectphenomenon for materials for radiation services, because it
is a major contributor to potential dimensional instability ofmaterials under irradiation at such temperatures that thermal
creep is not strongly anticipated. For silicon carbide (SiC)based nuclear components, the irradiation creep may be
important, in particular when a significant temperature
gradient exists and the secondary stresses developed bydifferential swelling can be severe. Flow channel insert inliquid metal blankets of fusion energy systems is an example
of such applications.
Studies on neutron irradiation creep of SiC have so
far been extremely limited and insufficient. The
experimental method of estimating the creep parameters
based on the stress relaxation in elastically bent strip
samples developed by Price[1] was later adopted to
examine the thermal creep behavior of refractory ceramic
fibers and was named bend stress relaxation (BSR) method.
In a recent work, Katoh et al. applied it for studying theirradiation creep of high purity, stoichiometric CVD SiC,
demonstrating that the BSR technique is effective todetermine the irradiation creep parameters [2,3].
Based on the previous demonstration of theexperimental technique and the recognized importance of
the irradiation creep, a more detailed study on the BSR
irradiation creep of SiC ceramics and composites wasplanned as the Phase-I program of Task 2-3 on dynamic
deformation of fusion materials in the TITAN Collaboration
program. The objective of the Phase-I study is to gain
understanding of the transient creep and stress relaxation
behavior of SiC ceramics, model composites, and composite
constituents during neutron irradiation. More specifically,
the study aims at determining the dose, temperature, andstress dependent BSR behavior of those materials and thecorrelation between the point defect swelling and thetransient creep deformation.

3. Results
Figure 1 shows the relationship between the stressrelaxation ratio and the initial flexural stress of R&H SiC
after various irradiation conditions [5]. The result show thatthe BSR ratios are about the same at 300C and 500C in
spite of swelling difference and it does not have initial stressdependence. Detail analysis of the irradiation behavior
compared with unirradiated data[4] and micro structuraldevelopment is on going. The phase-I result indicated thatthe BSR method in a conventional pre-straining
configuration may be used to determine the steady state
creep compliance.
0.50

800,1200䉝

0.45

Stress Relaxation Ratio

0.40
0.35

500䉝0.94dpa

0.30

R&H 300C 0.011dpa
R&H 300C 0.11dpa
R&H 500C 0.011dpa
R&H 500C 0.11dpa
R&H 500C 0.94dpa
R&H 800C 1.4dpa
R&H 1200C 1. 9dpa

0.25
0.20

300,500䉝
0.11dpa

0.15
0.10

300,500䉝
0.011dpa

0.05
0.00
0

100

200

300

400

Average St ress [ MPa]

Fig.1 Stress Relaxation Behavior of CVD-SiC after HFIR
Irradiation[1] R.J. Price, Nuclear Technology 35 (1977) 320-336[2]Y. Katoh, Y.B.Choi, T. Hinoki, Fusion Materials SemiAnnual Prog. Reports, DOE/ER-0313/45 (2008) 140-145[3]Y. Katoh, T. Hinoki, K. Ozawa, Y.Choi, A. Hasegawa,
L. L. Snead, Properties of Advanced SiC Fiber Composites
Irradiated at High Temperatures: Results from US/Japan
HFIR-18J Experiment, J. Nuclear Materials (submitted)[4]K. Abe, S. Nogami, A. Hasegawa, T. Hinoki, T. NozawaStudy on Stress Relaxation Behavior of Silicon Carbide by
BSR method, J. Nuclear Materials (submitted)[5]Y.Katoh, T.Hinoki, A.Hasegawa et al. to be submitted.

2. Experimental
The standard “SiC Bend Bar” type capsule housing
configuration were employed. Inside the standard sleeve,
which holds two ceramic bend bar samples in the standard
configuration, a rectangular casing is accommodated. Four
BSR assembly units are accommodated in each coffin. Each
BSR assembly is of size approximately 48 mm x 5.1 mm x 1
mm. The BSR assembly units are stacked together withCVD SiC liners/separator plates at the top, bottom, andbetween the units.
Materials to be studied and specimen loading to eachrabbit are CVD processed SiC, polycrystalline (R& H andCoorstek: beta SiC ) and single crystal (Cree : 6H SiC) and92

Common Task : MFE/IFE system integration modeling
Category : TITAN
Task : Common Task
Name: Akio Sagara, Hidetoshi Hashizume, Takayoshi
Norimatsu, Richard Nygren
Affiliation: NIFS, Tohoku Univ., Osaka Univ., Sandia
National Laboratory (SNL)

highlighted including maintainability, fabricability withprospect towards DEMO. Development of long-life blanket
and unscheduled blanket replacement are common
engineering key issues.
(4) Evaluation of tritium permeation loss rate was
performed on the Flibe blanket and LiPb blanket systems,
and it was found that rate limiting processes depending on
tritium concentration profiles are key issues in modeling [3].

1. Purpose
Aiming at the formation of the fusion engineering basis
which is necessary for the development of the MFE and IFE
reactors, it is designated as purpose that the integrated
engineering model of reactor system is constructed withexecuting the tritium and thermofuid system designs underthe boundary conditions of burning core plasmas and outvessel environments. Those activities cooperate with
science and engineering experiment researches on
estimating and controlling the time and spatial behaviors oftritium and energy flow formed in nuclear reactions. The
uniqueness of this task is (1) to perform modeling of theintegrated engineering system for design optimization (2) bycrossly connecting each task in this project (3) withimproving consistency of elemental device researches and(4) making feed back from each task.

4. Prospect and expected results
By combining model components, which are expected
to be improved in each task on microscopic behaviors oftritium and heat transfer in blanket systems, both ofdeveloping an integrated system model and establishing its
methodology are expected regarding macroscopic behaviors
between each element in the recycling loop for blanket
systems. At the same time, by making feedback of key
issues to each task, it is expected to enhance task activities
on developing tritium and thermofluid system with highconsistency between each task.
The integrated system model with high consistency isused for optimization of mass and heat transfer system in
MFE and IFE reactor designs. Furthermore, creation of
breakthrough on reactor designs and proposal of new
research issues are expected. As a result, the formation of
the fusion engineering basis is expected to be pushedforward.

2. Task plan
The former half of this task consists of(1) Identification of key issues and key parameters,(2) Identification of baseline designs and operating
conditions in such as FFHR, ARIES, KOYO,(3) Execution of analysis of key issues on tritium and heat
systems.
The later half consists of(1) Integration of results from TITAN tasks into design
process,(2) Integration of blanket modeling,(3) Providing researchers with information needs.

Table 1 The list of key 25 items to be checked for reactor
system integration modeling.

3. Achievements(1) Experimental models in each task were reviewed andlisted up major parameters for model integration withselecting models and physics to be included. This wascollected in the form of a spreadsheet that lists 25 items to
be checked (Table 1).
(2) To identify modeling targets, a seminar series in Journalof Atomic Energy Society of Japan was arranged mainly by
this task members, and published for the total 12 issues withthe main title of "The Fusion Reactor Wall is Getting Hot ! - A Challenge towards the Future for Numerical Modeling",
covering MFE and IFE reactor designs, edge plasma, PWI,
materials damage, neutronics, tritium breeding, heatremoval [1]. This article included results of discussion in thepast TITAN workshops.
(3) The first review was performed for the recent
stellarator/heliotron designs of FFHR, HSR, ARIES-CS [2].
Design optimization and engineering feasibility are1) A. Sagara, T. Norimatsu, S. Sharafat, et al., J. of Atomic
Energy Society of Japan, 50(6)(2008) to 51(7)(2009).
2) A. Sagara, Y. Igitkhanov, F. Najmabadi, Fusion Eng.
Des., in press.
3) S. Fukada, Y. Edao, A. Sagara, Fusion Eng. Des., inpress.

93

94

CHAPTER 6

DIII–D

6.1 Objectives
Collaborative activities on the DIII-D program were extended to establish the scientific basis forthe optimization of the tokamak for fusion energy, using a non-circular cross-section plasma withhigh triangularity, double-null divertor configuration, and various current drive system. These
activities were aimed towards understanding the physics of steady and high performance plasmas
and determining methods of steady-state operation over the last decade. 

6.2 Activities
The Japan Atomic Energy Research Institute (JAERI), from October 2005 Japan Atomic Energy
Agency (JAEA), extended an agreement with the U.S. DOE to collaborate on the DIII-D tokamak
at General Atomics (GA) in San Diego. This Agreement has provided close collaborative work on
the research programs at JAERI (later JAEA) and GA for 30 years. In the last 10 years, JAEA has
sent at least a total of 100 person-weeks of physicists and engineers to GA.
Joint research activities were carried out through participation in the DIII-D program and exchange
of information. Progress has been made in several areas including advanced tokamak physics,
divertor properties, confinement improvement such as H-mode, high beta physics and control,
electron cyclotron heating and current drive, diagnostics development, and tokamak stability theory.
These collaborations with DIII-D also complemented the research programs on JT-60U.
This experience built enduring mutual respect and friendships between JAEA and GA scientists
and engineers. This collaboration has indeed strongly progressed in the last 10 years, leading tosignificant scientific achievements as well as contributing to Japan’s JT-60 program and improving
the world fusion program.

6.3 Administration
The Steering Committee Meeting is held at General Atomics, San Diego every year throughout theperiod of collaboration between the U.S.DOE and JAERI/JAEA in order to coordinate thecollaborative work program. The committee comprises representatives of JAEA, DOE and GA.
The steering Committee discussed the accomplishments of the collaboration and the potential
benefits of the collaboration for advancing plasma physics in general, and for the ITER program
specially. The committee reviewed and recommended approval of the proposed exchanges fromJAEA to DIII-D in each fiscal year. The meeting was sometimes organized in conjunction with the“DOE-JAERI Technical Planning of Tokamak Experiments” meeting and the DIII-D advisorycommittee meeting. It emphasized technical discussions and closer collaborations.

6.4 Accomplishments and Highlights
The main subjects of collaboration in the last 10 years have emphasized progresses towards

95

higher-beta, a higher confinement and steady-state plasmas. During 2001-07, joint research has
supported both the DIII-D and JAEA program efforts in furthering Advanced Tokamak (AT)research, in particular the study of edge localized mode 㧔ELM 㧕stability, the development ofparticle control, the suppressions of Neoclassical Tearing Mode (NTM) and Resistive Wall Modeinstabilities (RWM), vessel activation studies, edge stability physics and edge current density
measurements, transport barrier studies, ITER Hybrid scenarios, and ECH technology, NBI andadvanced control technology.
On the occasion of the successful completion of JT-60 experiments in 2008, after 23 years ofoperations, the DIII-D team commends the JT-60 team on their many superb accomplishments inadvanced tokamak physics research fully exploiting the JT-60 device and pointing the way towards
an attractive future fusion energy source.
During 2008-09, joint research has continuously supported by both the DIII-D and JAEA program,that is effort toward progress in Advanced Tokamak (AT), in particular the study of rotation effects
on RWM, QH-mode plasmas, edge stability physics, momentum transport studies, advanced
control studies and efforts of Test Blanket Module (TBM) ripple. These activities are of direct
benefit to the DIII-D and JT-60SA programs and have supported resolution of ITER physics issues.
One of the outstanding achievements in recent years has been the discovery that a low toroidal
rotation of 0.3% of the Alfve’n velocity has an effect on the suppression of RWMs. This rotation
value is much smaller than previous predictions by theory and from experiments of magnetic
braking through the application of asymmetric magnetic fields, the so-called error fields. These
results obtained through collaborative work on JT-60U and DIII-D have had a large impact on thedesign of the advanced tokamak reactor where the RWM might be stabilized and controlled by therotation.

Table discussion for RWM physics. (2010, General Atomics)

Particle and heat transport is another important area of research under this collaborative framework.
Investigations of the transport barrier with a pedestal structure near the plasma edge are important
subjects. Several small ELM or ELM–free regimes such as grassy ELM, QH-mode and type II

96

ELMs with good confinement properties have been obtained on DIII-D, JFT-2M, JT-60U and othertokamaks. All these regimes show considerable reduction of the instantaneous ELM heat load on
the divertor target plates when compared to regimes with conventional type I ELMs. These small or
ELM-free regimes can be categorized in an operational space with non-dimensional pedestal
parameters and with specific requirements in plasma shape/configuration.
Discharges that simulate advanced operating scenario with large bootstrap current, high beta andhigh confinement have been jointly investigated in addition to hybrid scenarios with moderately
high beta, higher performance and partly inductive current drive. Advanced tokamak plasma withhigh beta, wall-stabilized discharges with fully non-inductive current drive that project tosteady-state operation in ITER have been sustained for more than a current relaxation time.
A number of pioneering results have been achieved through the collaborative work between the
DIII-D and JT-60U devices, in particular investigations on NTM physics with electron cyclotron
current drive (ECCD), as a result of the DIII-D high-power EC system, high resolution diagnostics
and advanced real-time NTM control capabilities. In collaboration with DIII-D and JT-60 and othertokamaks, the marginal island width for NTM has been investigated, which is important inestimating the required EC power and establishing a working scenario for NTM stabilization. It
was found that the marginal island is about twice the ion banana width. In addition, requirements
for real-time NTM stabilization in ITER have been investigated. This research has led to theapplication of ECCD at the mode rational surface before the NTM onset for preemptive
stabilization of the NTMs. This capability has been effectively demonstrated on both JT-60 and
DIII-D in high- s. More recently, NTM stabilization by modulated ECCD has been
demonstrated as a result of the close research collaborative efforts between DIII-D and JT-60.

97

Stabilization of Neoclassical Tearing Modes by Electron Cyclotron Current Drive
Category : Doublet III
Year-Number : 2001-DO-4, 2003-DO-6, 2004-DO-3
Name: A. Isayama, R.J. La Haye*, R. Prater*
Affiliation: Japan Atomic Energy Research Institute,*General Atomics

location were performed in real time [7]. Typical example
is shown in Fig. 2. In the discharge, the beta value wasraised to the no-wall ideal MHD limit by suppressing theonset of an m/n = 2/1 NTM. Soon after the switch-off of the
ECCD, an m/n = 2/1 NTM appeared. This result shows theeffectiveness of the preemptive ECCD.

Neoclassical tearing mode (NTM) is anmagnetohydrodynamic (MHD) instability which appears inhigh-E plasmas with positive magnetic shear (E is the ratioof the plasma pressure to the magnetic pressure). Since theNTMs degrade the plasma confinement through theformation of magnetic islands, stabilization of the NTMs isrequired to sustain a high-E plasma. Localized current driveat the mode rational surface using electron cyclotron (EC)waves, electron cyclotron current drive (ECCD), is
considered to be the most promising method for NTM
stabilization due to the capability of high magnitude ofcurrent drive density and high accuracy of current drive
location.
Both JT-60U and DIII-D devices have the capabilityof detailed investigation on NTM physics because theyequip (a) high-power heating system to obtain a high-beta
plasma, (b) high-power EC wave system to actively
stabilize NTMs, (c) high temporal and spatial resolution
diagnostics to measure and control NTMs and (d) advanced
plasma control system for real-time NTM stabilization. A
number of leading results have been reported from the bothdevices. For example, most recently, NTM stabilization bymodulated ECCD was demonstrated [1, 2]. Against the
backdrop of these results, close research collaboration has
been continued between JT-60U and DIII-D.
It is known that NTM islands have the property of
spontaneous shrinkage at small island width due to several
stabilization effects, and such shrinkage has also been
observed experimentally. Investigation on the island width
at which the spontaneous shrinkage begins, which isreferred to as the marginal island width, is important inestimating the required EC wave power and establishing the
scenario for NTM stabilization. In collaboration withASDEX-U (Max-Planck-Institut für Plasmaphysik,
Germany), DIII-D and JT-60U, the marginal island width
for an m/n = 3/2 NTM was investigated. Here, m and n are
the poloidal and toroidal mode numbers, respectively. It
was found that the marginal island is about twice the ion
banana width (Fig. 1) [3]. In addition, based on the results
and experiences in ASDEX-U, DIII-D and JT-60U,
requirement for real-time NTM stabilization in ITER was
also investigated [4].
Stabilization of NTMs by ECCD is usually achievedby injecting EC waves inside the NTM islands. As a new
strategy, ECCD at the mode rational surface before theNTM onset, what we call preemptive stabilization, wasdeveloped and the effectiveness was successfully
demonstrated in JT-60U [5, 6]. Preemptive stabilization ina higher-E regime was demonstrated in DIII-D withparticipation of JT-60 staffs. Experiments using a newly
developed real-time control system were successfully
conducted, where equilibrium reconstruction with current
density measurement and identification of the mode

Fig. 1. Marginal island widths in ASDEX-U, DIII-D
and JT-60U versus twice the ion banana width.
Expected marginal island width in ITER is also
shown. [from Ref. 3]

Fig. 2. Evolution of plasma behavior of a preemptive
ECCD discharge in DIII-D. (a) line-averaged density
and DD emission, (b) EC wave power and timeaveraged neutral beam power, (c) central andminimum value of safety factor, (d) amplitudes ofn = 2 and n = 1 tearing modes and (e) normalized beta
and four times the internal inductance (an estimate of
the beta limit for the ideal n = 1 kink mode in theabsence of a conducting wall). [from Ref. 7]1) Isayama, A. et al., Nucl. Fusion 49 (2009) 055006
2) Volpe, F. et al., Phys. Plasmas 16 (2009) 102502
3) La Haye, R.J. et al., Nucl. Fusion 46 (2006) 451
4) La Haye, R.J. et al., Nucl. Fusion 49 (2009) 045005
5) Nagasaki, K. et al., Nucl. Fusion 43 (2003) L7
6) Isayama, A. et al., Phys. Plasmas 12 (2005) 056117
7) Prater, R. et al., Nucl. Fusion 47 (2007) 371

98

High-brightness and low-divergence lithium neutral beam for a Zeeman polarimetry on JT-60U
Category : Doublet III
Year-Number : 2005-DO-9,
Name: A. Kojima, K. Kamiya, T. Fujita, H. Kubo, H.
Iguchi*.
Affiliation: Japan Atomic Energy Agency, *National
Institute for Fusion Science.

account because a low divergence angle of the neutral
lithium beam is required in terms of the narrow spectrum of
the beam emission and the high transmission of the long
beam line of 6.5 m. Although the beam energy of 10 keV isrelatively low, an extraction electrode installed in front of
the ion source can produce a large current beam over 10
mA.
The newly-developed ion gun has been operated on atest stand which simulates the diagnostic geometry on JT60U. The ion beam current of 10mA at a beam energy of
10 keV is successfully extracted from the ion source andfocused by Einzel lens. The FWHM (Full Width at Half
Maximum) radius of the ion beam at the neutralizer isabout 9 mm. A sodium vapor neutralizer neutralizes thecollimated ion beam fully at the temperature of 300 oC. The
neutral beam profiles have been measured at two locationsof the beam line at 2.3 m (beam monitor position) and 6.5m (plasma region) from the neutralizer. The HWHM radiusof the neutral beam of 26mm and the equivalent beam
current of 3 mA with the beam divergence angle of 0.2
degree which is the half-angle divergence have beenobtained. Those parameters satisfy the requirements of the
Zeeman polarimetry. Furthermore, a long pulse extraction
with a current of 10 mA and duration of 50 seconds has
been attained [2].
After developing the detectors, the LiBP has been
installed on JT-60U. The LiBP has 20 viewing chords inthe edge region r/a = 0.8 ~ 1.0 with a spatial resolution of 1
cm. Etalon and band-pass filters are applied to separate thepolarized spectrum of the beam emission. In order to tune
the etalon filters, a new technique in which the Doppler
shifted spectrum is varied by sweeping the beam energy
has been developed and has demonstrated the availability[3].
The electron density profiles in the edge region havebeen measured by using the LiBP with a temporal
resolution up to 0.5 ms. In addition, an ELM cycle in casesof type I and grassy ELMs have been observed [4]. The
collapse of density pedestal of grassy ELMs is smaller(<20%) and the radial extent is narrower (ѝ 5 cm) thanthose of type I ELMs (~30%, >15cm). The measurement of
the edge current density has been also achieved by using
the LiBP [3]. Time evolution of the edge current density
profiles have been determined for the current ramp
up/down in the OH plasmas. Moreover, the edge current
density profile having the local peak of 0.15–0.25 MA/m2
at r/a ~ 0.9 has been identified in the H-mode plasma. The
local peak might be caused by the strong pressure gradientin the edge pedestal region.

Lithium beam probes (LiBP) are powerful diagnostic
for pedestal studies since the electron density and the pitch
angle of the magnetic field line in edge plasmas can bemeasured from the beam emission signal and its
polarization angle. In order to measure the edge plasmas
with high-spatial and high-temporal resolutions, highperformance neutral lithium beams are required. In theprevious works on DIII-D, direct measurements of the edge
current density was carried out by use of 30 keV, >10mA
lithium beams [1]. Recently, JT-60U planned to install the
LiBP for the measurement of the edge electron density andcurrent density. For the LiBP on JT-60U, the optimum
beam energy was lower than that for DIII-D because oflower pedestal density. However, the large beam current
was also required to obtain a high S/N ratio. Such beams
are strongly affected by the space charge effects and easy
to spread. Therefore, a high-brightness and low-divergenceneutral lithium beam source with low energy of 10 keV has
been developed on JT-60U.
In order to obtain a large current over 10 mA, athermionic ion source heated by an electron beam has beendeveloped. The diameter of the ion emitter is 50 mm which
is made from porous tungsten with porosity of 30 %. The
porous tungsten disk is mounted on the molybdenum
holder as shown in Fig. 1. The acceleration voltage of 1.5
kV for the electron beam is applied between the disk and atungsten filament behind the disk. The surface temperatureof the disk reaches to 1500 oC with the typical heating
power of 1.3 kW. The extracted ion current can exceed 10
mA in this case. The maximum power of the electron beam
heating is 5 kW which is enough to make E eucryptite(Li2OxAl2O3 x2SiO2) soaked in the disk.
The beam optics has been designed after detailed
numerical simulation taking the space charge effects into

[1] D. M. Thomas et.al., Phys. Rev. Lett. 93, 065003(2004)[2] A. Kojima et al., Rev. Sci. Instrum. 79, 093502 (2008).
[3] K. Kamiya et al., Rev. Sci. Instrum. 81, 033502 (2010).
[4] A. Kojima et al., Nucl. Fusion 49, 115008 (2009).

Fig. 1. The electron beam heated ion source with a 50 mm
porous tungsten disk and a molybdenum holder.

99

Numerical Method for the Stability Analysis of Ideal MHD Modeswith a Wide Range of Toroidal Mode Numbers in Tokamaks
Category : Doublet III
Year-Number : 2004-DO-2, 2005-DO-2,
Name: N. Aiba, S. Tokuda, M. S. Chu1, P. B. Snyder1
Affiliation: Japan Atomic Energy Agency, 1General
Atomics

ELM phenomena. For not only the experimental analysis ofexisting devices but also the design of ITER and JT-60SA,
MARG2D realizes the stability analysis of the various
kinds of ideal MHD modes that restrict the beta limit andthe pedestal performance.

In tokamaks, an ideal magnetohydrodynamic(MHD) instability attracts attention as one of key issues fora high performance operation. This is because a low-n
MHD mode often restricts a plasma performance (betalimit), and intermediate / high-n MHD modes sometimes
determine an edge pedestal performance, where n is atoroidal mode number. To identify the stability of theseMHD modes, we have invented the effective numericalmethod for the stability analysis of ideal MHD modes withthe physical model based on the two-dimensional
Newcomb equation in combination with the conventional
compression-less ideal MHD model. The MARG2D code
has been developed based on this numerical method, andrealizes to analyze the stability of ideal MHD modes with awide range of toroidal mode number n [1,2]. In thiscollaboration, we execute the benchmarking test of thisMARG2D code with the DCON code [3] for a low-n modestability analysis, and that with the ELITE code [4,5] for anintermediate / high-n mode analysis.
Figure (a) shows the dependence of the E N limit on
the wall position da. These dependences identified with
MARG2D and DCON are almost identical to each other.
Unfortunately, since the DCON code used in thisbenchmarking (ver. 3.2) cannot output the marginally stableeigenfunction, we cannot compare the radial structure of
the eigenfunction. However, in a up-down symmetricequilibrium, the benchmarking tests between MARG2D
and the ERATOJ code [6] have been executed in Ref. [2],and the radial structures of the marginally stableeigenfunctions have been identified as almost same as eachother.
Figure (b) shows the toroidal mode number ndependence of the growth rate J normalized with thetoroidal Alfv´en frequency on the magnetic axis ZA. The
agreement between MARG2D and ELITE is quite good,
and as shown in Ref. [7], the radial structures of the most
unstable eigenfunction obtained with MARG2D and ELITE
are almost identical to each other. The results of thesebenchmarking tests show the validity of the MARG2D codefor the stability analysis of not only low-n but alsointermediate / high-n MHD modes [7].
With this code, we investigated the MHD stability
property in JT-60SA, the complemented device for ITER
focusing on effect of the plasma shape. These stability
analyses show that the highly shaped plasma designed forachieving high performance discharges in JT-60SA is
suitable for stabilizing not only low toroidal mode number
MHD modes, which restrict the E N limit of discharges, butalso intermediate to high toroidal mode number MHD
modes, which relate to the edge pedestal performance andFig. 1: Dependence of the EN limit on the wall position d/a.
Each dependence of the EN limit restricted by the n =1, 2, 3 MHD modes stability estimated with MARG2D isalmost identical to that calculated with DCON.

Fig. 2: Dependence of J / ZA on n calculated with
MARG2D (solid line) and ELITE (broken line). The
agreement between both codes is quite good.
[1] S. Tokuda and T.Watanabe, Phys. Plasmas 6, 3012
(1999).
[2] N. Aiba, S. Tokuda, T. Ishizawa, and M. Okamoto,Comput. Phys. Commun. 175, 269 (2006).
[3] A. H. Glasser and M. S. Chance, in Bull. Am. Phys.
Soc., volume 42, page 1848, 1997.
[4] H. R.Wilson, P. B. Snyder, R. L. Miller, and G. T. A.
Huysmans, Phys. Plasmas 9, 1277 (2002).
[5] P. B. Snyder et al., Phys. Plasmas 9, 2037 (2002).
[6] R. Gruber and J. Rappaz, Finite Elements Methods in
Linear Ideal Magnetohydrodynamics, Berlin: Springer,
1985.
[7] N. Aiba, S. Tokuda, T. Fujita, T. Ozeki, M. S. Chu, P.
B. Snyder, and H. R. Wilson, Plasma Fusion Res. 2, 010(2007).

100

Rotation effect on RWM stabilization
Category : Doublet III
Year-Number : 2003-DO-5, 2004-DO-6, 2006-DO-2
Name: M. Takechi, G. Matsunaga, N. Aiba, H.
Reimerdes1, A.M. Garofaro1, G. L. Jackson2, M.
Okabayashi3, E. J Strait2, M. S. Chu2 and Y. In4
Affiliation: JAEA, 1Columbia University, 2General
Atomics, 3PPPL, 4FARTECH, Inc.

stabilization of RWM is demonstrated for 50 times theskin time of the first wall. These results indicate that forlarge plasmas such as in future fusion reactors with low
rotation, the requirement of the additional feedback
control system for stabilizing RWM is much reduced.
Around the same time, similar experiments were
performed on DIII-D. High-Ǫ DIII-D experiments with
the new capability of balanced neutral beam injection also
show that the resistive wall mode (RWM) remains stable
when the plasma rotation is lowered to a fraction of a percent of the Alfv´en frequency by reducing the injection ofangular momentum in discharges with minimized
magnetic field errors [7,8]. A toroidal rotation frequencyof less than 10 krad/s at the q = 2 surface corresponding to
0.3% of the inverse of the toroidal Alfve´n time issufficient to sustain the plasma pressure above the ideal
MHD no-wall stability limit (Fig. 1). The low-rotationthreshold is found to be consistent with predictions by akinetic model of RWM damping. Previous DIII-D
experiments yielded a high plasma rotation threshold (oforder a few per cent of the Alfv´en frequency) for RWM
stabilization when resonant magnetic braking was applied
to lower the plasma rotation. They propose that thepreviously observed rotation threshold can be explained as
the entrance into a forbidden band of rotation that resultsfrom torque balance including the resonant field
amplification by the stable RWM.

To realize an economical fusion reactor,
stabilization of the low-n kink-ballooning mode isnecessary: An economical fusion reactor, in its steadystate, relies largely on the spontaneously flowing bootstrap
current for its plasma current that produces the confining
magnetic field, because this can reduce the externallydriven current. But such plasma has generally a hollow
current profile and is susceptible to the low-n kinkballooning mode, which can limit the achievable beta.
The growth rate of the external kink-ballooning mode canbe reduced with a close-fitting conducting wall, and theresulting mode, the so-called resistive-wall mode (RWM),
has a growth time corresponding to the time constant of
the relaxation of the wall current [1]. There are twodifferent procedures for stabilizing RWM. The first is the
feedback control stabilization using externally applied
nonaxisymmetric magnetic fields with coils in order tocompensate for the diffusion of flux [2]. The second isstabilization of RWM by toroidal plasma rotation.
Bondeson and Ward showed that RWM could be fullystabilized with resistive walls when the plasma rotation is
sufficiently large [3]. Both theories and experiments
imply that the critical rotation velocity is around 1% – 2%of the Alfve’n velocity. This estimated critical rotation iscomparable to a predicted toroidal rotation of 2% of the
Alfve’n velocity at plasma center and much larger than
0.3% of that in the peripheral region including the q =integer surface for the ITER advanced scenario. The
most significant problem in the previous experiment is thatinvestigation of the critical rotation is performed withmagnetic braking by adding an asymmetric magnetic field,
the so-called error field. It has been pointed out that theerror field plays a very important role in the destabilizationof RWM and should be substantially reduced near the nowall limit. Since RWM stability itself is affected by
the error field, which is the origin of magnetic braking, weshould not use magnetic braking in the investigation ofcritical rotation.
A very low rotation threshold was obtained in the JT60U in an investigation of the critical rotation forstabilizing RWM by controlling the toroidal plasma
rotation with changing the combination of tangential
neutral beams (NBs) without magnetic braking [4-6]. The
observed critical rotation is Vt~20 km/s and corresponds
to 0.3% of the Alfve’n velocity at the q = 2 surface,much smaller than the previous prediction with magnetic
braking (Fig. 1). This low critical rotation does notincrease as increases toward the ideal wall limit. Also an
ITER relevant low rotation (~0.4% of the Alfve’n velocity)

1

E

0.8
CE

ideal-wall
N

x
x

0.6
0.4

xx x

0.2
0
-60

no-wall

x EN

-40
-20
0
V (km/s) at q=220

tFig. 1. Trajectories of the CE versus toroidal rotation at q = 2 for JT-60U(left) and DIII-D (right). The crosses and squares denote the onset points
of RWM on JT-60U and DIII-D, respectively [6,8].

[1] D. Pfirsch and H. Tasso, Nucl. Fusion 11, 259 (1971).
[2] C. M. Bishop, Plasma Phys. Controlled Fusion 31, 1179
(1989).
[3] A. Bondeson and D. J. Ward, Phys. Rev. Lett. 72, 2709
(1994).
[4] G. Matsunaga et al., Europhys. Conf. Abstr. 30l, 02.003(2006).
[5] M. Takechi et al., Phys. Rev. Lett. 98, 055002 (2007).
[6] M. Takechi et al., in Proceedings of the 21st IAEA
Fusion Energy Conference, Chengdu, China, 2006,
http://www-pub.iaea.org/MTCD/Meetings/FEC2006/
ex_7-1rb.pdf.
[7] H. Reimerdes et al., Phys. Rev. Lett. 98, 055001 (2007).
[8] A. M. Garofalo et al., in Proceedings of the 21st IAEA
Fusion Energy Conference, Chengdu, China, 2006,
http://www-pub.iaea.org/MTCD/Meetings/FEC2006/
ex_7-1ra.pdf.

101

102

CHAPTER

7 HFIR

This program has contributed for thirty years to the development of fusion reactors by the scientificand engineering products about the irradiation damage on the structural materials obtained by U.S.
and Japanese Scientists.

7.1 Objectives
The objective of this collaboration is to design, conduct and evaluate joint irradiation experiments in
the High Flux Isotope Reactor (HFIR) of the Oak Ridge National Laboratory for the purpose ofinvestigating the irradiation response of Japanese and U.S. structural and special purpose materials
to high levels of atomic displacement and Helium content in order to establish the database on theproperties and behavior of such materials and to evaluate their performance for the use in future
fusion reactors.

7.2 Activities
The collaborative Program consists of the following;(1) Planning of the collaborative program;(2) Design and conduct of irradiation experiments in HFIR;(3) Technology development for evaluation, post-irradiation testing;(4) Exchange of personnel and information necessary to carry out the collaborative program; and(5) Exchange of results arising from the collaborative program.
Five phases of the collaborative Program have been completed. These phases had begun in ‘83, ‘88,
‘94, ‘99 and 2004, respectively. Post phase V activity has been started in 2009 and is expected tocontinue until 2014.
Phase I of the program focused on the effects of high concentrations of transmutation produced
helium coupled with displacement damage on mechanical properties and swelling behavior of theJapanese and U.S. austenitic stainless steels. Phase II was also devoted to the understanding of theirradiation effects of austenitic alloys. Spectral and isotopic tailoring techniques were developed andutilized to reproduce the ratio of the generation rates of helium and the displacement damage(He/dpa ratio) typical of the fusion reactor environment. Also, irradiation behavior of the variety of
weld materials was evaluated. In Phase III of the program, examination of the irradiation response ofadvanced materials for DEMO reactors was initiated. Materials of the reduced activation
ferritic/martensitic (RAF/M) steels, vanadium alloys, SiC/SiC composites and titanium aluminides
were included. Also, in situ test techniques to evaluate thermal conductivity and electro-resistivity ofceramic materials (SiC/SiC composites, Alumina etc.) during irradiation have been developed in thecollaboration, and the measurements were carried out. The objectives of the Phase IV program were(a) development of improved methods for predicting the in-service operation of first wall andblanket structure utilizing RAF/M steels and development of a high quality database on themechanical behavior of F82H (a RAF/M steel developed by JAEA and JFE corp.), including theeffects of helium generation and (b) resolution of fundamental issues of flow and fracture in BCC

103

alloys and in particular those issues related to the simultaneous generation of displacement damage
and helium in F82H and related alloys. As a major goal of Phase V program, both Japanese and U.S.
sides recognized the importance to provide the critical irradiation performance data on RAF/M steels
without which it will not be feasible to proceed with the design, construction and operation of the
TBMs in ITER. To utilize the irradiation program to explore nano-scale microstructural strategies
designed to minimize the impact of high levels of displacement damage and helium damage on
mechanical behavior was determined to be another goal of Phase V program. Results of this work
also provided a scientific basis of innovative and RAF/M steels for critical structural components for
DEMO.

7.3 Administration
The general management of the Collaborative Program has been carried out by a Steering
Committee. The Steering Committee has been composed of four members, two each are assigned by
JAEA and DOE and conduct following assignments.
(1) Plan the Collaborative Program, and develop the annual work plan which shall be included theannual budget and the financial contributions of JAEA and DOE.
(2) Review the cost and the projection of expenditures.
(3) Review plans for joint paper publication.
(4) Discuss personal assignments.
(5) Recommend the annual program of work, budget and personnel assignments and other suchmatters to JAEA and DOE approval.
(6) Report to the Japan-U.S. Coordinating Committee on Fusion Energy through the Contact Persons
on the technical progress in the current annual work and make recommendations for approval of thenext annual work plan and budget and for the financial contributions of JAEA and DOE to theCollaborative Program to the next annual program of work.

7.4 Accomplishments and Highlights
One of the major outcomes from Phase I of the program is the optimization of the chemicalcomposition and the heat mechanical treatment of the Japanese and U.S. austenitic stainless steels.
The features of phase II are (i) utilization of the spectral and isotopic tailoring techniques toreproduce the ratio of the generation rates of helium and the displacement damage (He/dpa ratio)
typical of the fusion reactor environment, and (ii) the evaluation of irradiation behavior of the variety
of weld materials. Results from phase I and II are utilized to establish service conditions of theaustenitic alloys for the first wall of ITER, although the postulated service conditions at the
beginning of the Program was considerably different from that of ITER.
One of the major accomplishments during phase III is the development of the Japanese and U.S.
RAF/M steels. These steels exhibited superior resistance for irradiation and is expected to have low
induced activities after fusion neutron irradiation. Another important result of phase III is theevaluation of electrical and thermal properties of ceramics under irradiation using the in-situ
measurement technique.
During the Phase IV program; (a) test method development to examine helium effect on104

microstructural and mechanical property changes, as well as small size specimen techniquedevelopment to increase the number of specimens loaded in the irradiation capsule by optimizing
specimen configuration; (b) development of innovative/advanced materials, such as SiC/SiC
composite exhibiting superior resistance for irradiation damages; and (c) extending the knowledge
about the irradiation performance of RAF/M (F82H was used as a reference alloy), including thestress level, damage level and temperature dependence of irradiation creep and the effect of heat
treatment condition on post irradiation tensile properties have been also accomplished.
Improvement of small size specimens (e.g. pre-cracked bend fracture specimens) has been also
carried out during Phase IV and utilized to evaluate post-irradiation fracture toughness of RAF/Ms
during Phase V of the program. Irradiation response, especially reduction of fracture toughness andductility has vital importance for the application of RAF/Ms to TBMs and in-vessel components of
the DEMO. During the Phase V, mechanical properties after irradiation to 20 dpa at temperatures
between 300oC and 500oC have been examined to expand irradiation materials database prepared in
the previous phases of the program. F82H and its variants, as well as advanced U.S.
ferritic/martensitic steels were used. The variants were irradiated for “tightening of heat treatment
condition” and “evaluating the effect of tantalum addition”. Results indicated that residual ductility
and fracture toughness of RAF/Ms including shift in ductile to brittle transition temperature (DBTT)
remained in the ranges appropriate for the fusion systems; DBTT (<100oC) was lower enough thanservice temperature and considerable level of residual ductility (reduction of area >50% at 7.9 dpa)
was maintained. As for the irradiation effect on these two of the critical mechanical properties,
RAF/Ms (e.g. F82H and ORNL 9Cr) exhibited their feasibility for in-vessel components to a damagelevel of 20 dpa. Variants of F82H and ORNL 9Cr exhibited superior performances, such as lower
post irradiation DBTT (lower than room temperature). This and the saturation tendency of ductility
and toughness degradation with damage levels are suggesting their feasibility to higher damagelevels. Result of irradiation induced microstructural change revealed the mechanism of the superior
irradiation response found in the specimens for “tightening of heat treatment condition experiments”.
As for advanced nano-composite ferritics (NCFs) and SiC/SiC composites, high stability ofnano-oxide particles during aging and irradiation has been demonstrated, as well as the outstanding
irradiation resistance of high purity/near stoichiometric SiC/SiC composite. Efforts for the resolutionof fundamental issues of flow and fracture of BCC alloys and for exploring nano-scale
microstructural strategies designed to minimize the impact of high levels of displacement damage
and helium damage made a good progress. Development of the technique to introduce helium atoms
in RAF/Ms with adjustable He/dpa ratio using Ni (NiAl alloy) plating on specimen surface has beensuccessfully demonstrated. Development of both atomistic model and macroscopic model of theirradiation effects has been also conducted. These modeling activities have been also carried out tounderstand fundamental issues of irradiation damages on flow and fracture of BCC alloys, as well as
to obtain fundamentals for the development of structural designing methodologies of intensely
irradiated components. After the period of phase V, examination of the irradiation effects on fatigue
and creep properties as well as critical short term properties of ductility and fracture toughness ofvarious joints are expected to be accomplished with precisely adjusted production ratio of helium
atoms and displacement damage rates relevant to fusion neutrons (10appmHe/dpa) to establish

105

database and macroscopic models of irradiated RAF/Ms for the development of TBMs. This and theexamination to higher damage levels (>50dpa and 500appmHe) is also going to be conducted tosupply the basic knowledges for DEMO application. Modeling activities are expected to play vitalroles to establish design methodologies of intensely irradiated structures and the development ofinnovative materials including NCFs and SiC/SiC composites.
List of accomplishments during five phases; Highlights for Phase IV and V are attached(i) Austenitic stainless steel(i-1) Irradiation response to high damage levels (to 50 dpa) (Phase I)(i-2) Behavior of weldment (Phase II)(i-3)Spectral tailoring experiment to obtain appmHe/dpa ratio for fusion (Phase I and II)(i-4) Fracture toughness of austenitic steels (Phase II)(i-5) Irradiation assisted stress corrosion cracking (IASCC) (Phase III)(ii) In situ testing(ii-1)In-situ electrical and thermal conductivity measurement of ceramics (Phase III)(iii) Reduced activation ferritic/martensitic (RAF/M) steel(iii-1) Development of RAF/M steels (Phase II and III)(iii-2) Fracture behavior of RAF/M steels (Toughness and ductile-to-brittle transition temperature)(Phase IV and V, Highlights No. 1, 2, 3 and 4)(iii-3) Tightening of heat treatment condition and the evaluation of the effect of tantalum (a minor
alloying element) (Phase V, Highlights No. 1, 4 and 5)(iii-4) Irradiation creep (Phase IV, Highlights No. 1 and 7)(iv) Test methods(iv-1) Small size specimen technology (Phase IV and V, Highlight No. 4 and 7)(iv-2) In situ helium implantation technique (Phase V)(v) Modeling(v-1) Behavior of helium atoms in steels (Phase V, Highlight No. 8)(v-2) Constitutive equation of irradiated RAF/M steel (Phase V, Highlights Nos. 1 and 9)(vi) Innovative/advanced materials(vi-1) SiC/SiC composite (Phase IV and V, Highlight No. 10)(vi-2) Nano-composite ferritics (Phase IV and V, Highlight No. 1)

106

Irradiation effects on deformation and fracture of reduced activation ferritic steels
Category: Fusion engineering/HFIRYear-Number㧦04-09 - No. 1
K.Shiba, E.Wakai, T.Sawai, M.Ando, H.Tanigawa, T.Hirose,
R.L.Klueh*, R.E.Stoller*,G.R.Odette**, S.Jitsukawa
JAEA, *ORNL, **UCSBReduced activation ferritic steels (RAFs) are candidate structural
materials for in-vessel components of a DEMO. The service
temperature is expected to range between 300 and 550oC while
14MeV D-T fusion neutron irradiation introduces displacement
damage to 100-150 dpa and damage from transmutation produced
atoms (e.g. He atoms with production rate of 10-15 appmHe/dpa) tocause reductions of elongation, fracture toughness and fatigue life, as
well as dimensional changes by irradiation creep and swelling[1].
Therefore, the DOE-JAEA collaborative experimental programusing HFIR has been conducted to investigate the irradiation
response of RAFs. Japan’s F82H was chosen as a reference heat with
objective of producing an irradiation materials database, while
analyzing deformation and fracture for the modeling of the irradiation
effects. The results indicate that degradation by displacement damage
is manageable for the doses examined [2]. Moreover,tightening/optimization of heat treatment conditions reduced
radiation-induced embrittlement, suggesting the feasibility of RAFs
for the DEMO[2, 3]. Analysis on deformation and fracture also
provided post-irradiation constitutive equations. This and the fracture
behavior are essential for developing a design methodology.
Effects of irradiation on tensile, fracture and creep properties are
summarized, as well as the analysis of deformation. Methods toimprove post irradiation fracture resistance are also introduced.
1) Tensile property: Below 400oC, irradiation often causes hardening
and reduction of elongation (see, Fig. 1). The reduction of elongation
has been recognized as an issue, however detailed analysis revealed
that relatively large ductility remained even after irradiation [4].
Moreover, tightening/optimization of the heat treatment condition
was found to keep post irradiation ductility even higher [3].

the mechanism of cracking to promote failure at crystallographic
boundaries, although it introduced no apparent change in DBTT-shift[4, 5]. On the other hand, reduction of the post irradiation DBTT has
been successfully achieved by tightening/optimization of heat
treatment condition before irradiation (see, Fig. 3) [5].

Fig.2
dependenceofof
DBTT
F82H
Fig. 2Damage
Damage level
level dependence
DBTT
forforF82H[2] [2].
F82H
smallerDBTT-shift
DBTT-shiftconventional
F82Hexhibits
exhibits smaller
thanthanconventional
steelssteels.

Fig.3 Improvement of
DBTT-shiftbytightening/optimization
Fig.3 Improvement of
Dof
Bheat
T Ttreatment- s h i f t[5]b ytightening/optimization
post irradiationofLowerheat treatment
[5].
DBTT
was
achieved.
Lower postirradiation
DBTT was achieved.

Improved by tightening ofheat treatment condition

Conventional heat treatment

3) Irradiation creep: Irradiation creep strain has been evaluated fromdiametral change of pressurized tube specimens. At 300 and 500oC,
creep strains were rather small and almost proportional to hoop stressbelow 380 and 180 MPa, respectively [6].
4) Modeling of deformation and fracture (Macroscopic models):
Analysis of the deformation of tensile specimens with macroscopic
defects (e.g. holes) has been conducted to evaluate constitutive
equation after irradiation [7]. The strain distribution was measured
with 3D image analysis equipment and optical microscopy. Either
Ludwik or Swift type constitutive equations was applied, andstress-strain relations have been successfully reproduced to fracturestrain levels. This provides the fundamentals required for a design
methodology for components under intense neutron irradiation [2].
5) Microstructure and alloy development: Microstructural
examinations including fractography have been conducted. The
results indicate the deteriorating effects of inclusions containing Ti
and N, as well as that by other complex inclusions [8]. Dispersion ofTi and Y containing nano-scale oxide particles in RAF has beensuccessfully achieved by mechanical alloying. One of the alloys,
14YWT exhibited superior strength at high temperatures [9].

Fig. 1 Engineering
stress-strain relations of
Fig.1 before
Engineering
F82H
and after
stress-strain relations
irradiation[2]of F82H before andafter irradiation[2].
Irradiation
reduces
Irradiation
reduceselongation(Oneof theelongation (One of theissues)issues).
2) Fracture toughness: Below 400oC, irradiation also reduces fracture
toughness and upper shelf energy, and increases the shift in ductile tobrittle transition temperature (DBTT). Fig. 2 shows DBTT-shift ofseveral ferritic steels by irradiation. It should be noted that
DBTT-shifts of RAFs are smaller than those of conventional steels.
14 MeV high energy D-T neutrons introduce He atoms at a high rateand is thought to cause additional toughness degradation. Doping of58
Ni and 10B introduces He atoms during irradiation of RAF in HFIR.
Fractography revealed that 300-400appmHe introduced a change in[1]S.Jitsukawa et al., J. Nucl. Mater., 329–333(2004)39–46[2]S.Jitsukawa et al., Nuclear Fusion 49 (2009) 115006[3]M.Ando et al., J. Nucl. Mater., 386–388 (2009) 315–318[4]R.L.Klueh et al., J. Nucl. Mater., 357 (2006) 156–168[5]N. Okubo et al., to be published[6]M.Ando et al., J. Nucl. Mater., 367–370(2007)122–126[7]G.R.Odette et al., J. Nucl. Mater., 307–311(2002)171–178[8]H.Tanigawa et al., J. Nucl. Mater., 367–370(2007)42–47[9]D.T.Hoetzer et al., J.Nucl.Mater.,367–370(2007)166–172

107

Fracture Toughness of HFIR Irradiated Tempered Martensitic Steels

effects. Size adjustment procedure developed for RPV steel[2] has successfully been applied to a large database of
F82H KJm measured on specimens of various size andgeometry [3]. The size adjustment procedure has been
applied to a subset of the JP-26 irradiated specimen data.
The CL adjustment is based on finite element analyses(FEA) of the crack tip stress field for actual specimen
geometry compared to an ideal small scale yielding
condition. The SV effect is adjusted by modified B-1/4
scaling as is incorporated in ASTM E 1921 Master Curvestandard. Details are given in ref [4]. Figure 2a shows Badjusted toughness data before (KJB) and after (KJr) the CL
adjustment for F82H-IEA irradiated to 7 dpa at 300 ºC.
The CL adjustment resulted in 'To   "  + " $than the unadjusted case. The 'To/'Vy of  !+ after
adjustment is consistent with larger CT specimen data as
shown in Figure 2b, while it is still smaller than the RPV
data. The effect of strain-hardening loss in irradiated TMS
can be accounted for using the change in flow stress,
resulting in more consistent 'To/'Vfl>  +, % $$
agreement with the theoretical study by Odette et al. [5]shown in Figure 2c. The CL-adjusted 'To data also showed
good agreement with a hardening based prediction model[6] shown in Figure 2d. This research is on going.

Category : Fusion engineering/HFIRYear-Number : 2004-09 - No.2,
Name: Takuya Yamamoto1, Mikhail A. Sokolov2, G.
Robert Odette1
Affiliation: 1University of California Santa Barbara, 2Oak
Ridge National Laboratory
Irradiation embrittelement, as characterized by upward
shifts ('To) in the cleavage fracture toughness master curve(MC), is one of the key issues that control the operation
window of the 8-9Cr-1-2W normalized and tempered
martensitic steels (TMS) in fusion reactor first wall
applications. At irradiation temperatures less than  
the 'To are primarily due to irradiation hardening, 'Vy.
One of the keys to understand and model the mechanism isto obtain the correlation between 'To and 'Vy.
Large number of small pre-cracked bend bar (PCBB)
specimens, with single or multiple cracks, of several TMS
were irradiated from 300 to 500 oC in HFIR target capsules,
JP26 and JP-27, up to          results for F82H IEA and F82H mod.3 heats. Figure 1ashows 'To of the IEA heat as a function of neutron dose atfour irradiation temperatures. There are clear trend showing
less embrittlement at higher irradiation temperaturecorresponding to the irradiation hardening trend, except: 1)
the 300ºC embrittlement trend shows no sign of saturation
up to 20 dpa, 2) the embrittlement insists beyond thetemperature of  ! " #  $%   %%turns to softening regime. The F82H mod.3 heat seems toshow less embrittlement than the IEA heat at the same doselevel; however this needs further confirmation.
250

250C
300C

400C
500C

'To (oC)

200
150
100
50
F82H IEA
0

0

5

10

15

20

25

dpa

Fig. 1 a) Toughness reference temperature shift, 'To, of F82H
IEA heat as a function dpa at four irradiation temperatures; b) 'To
vs. 'Vy relation for various TMS steels obtained using PCBB
specimens, compared to RPV database by Sokolov et al.[1]Fig. 2 a) 1T-conveted toughness data with MCs before (KJB) andafter (KJr) CL adjustment; b) 'To vs. 'Vy relations in CL-adjusted
PCBB or CT specimens of irradiated F82H-IEA; c) 'To vs.
'<Vfl> (flow stress change) compared with theoretical relation
study[5]; d) 'To in relatively high constraint specimens of F82H
irradiated at  -" #  $ (  '$%.+/

Figure 1b summarizes relation between 'To and 'Vy for the
TMS measured using similar small specimens, comparedwith reactor pressure vessel (RPV) steel data collected by
Sokolov [1] primarily using larger specimens. The TMS
data show 'To/'Vy ratio of    %&'%() (( %that for RPV steels of  * The major reasons for the low'To/'Vy ratio are believed to be due to 1) loss of strain
hardening capacity in the irradiated TMS, and 2) constraint
loss (CL) in the small specimens. The fracture toughness,
KJm, measured using small specimens is generally higher
than those obtained from larger, conventional specimens,
due to both statistical stressed volume (SV) and CL size

[1] Sokolov, M.A. et al., ASTM STP-1325(1999)167[2] Rathbun, H.J. et al., Eng. Fract. Mech 73 (2006) 2723
[3] Odette, G.R. et al., J. Nucl. Mater. 329-333 (2004) 1243
[4] Yamamoto, T. et al., accepted for J. Nucl. Mater. (2010)[5] Odette, G.R. et al., J. Nucl. Mater. 367-270 (2007) 561[6] Yamamoto T. et al., J. Nucl. Mater. 356 (2006) 27

108

Charpy impact properties of reduced-activation ferritic/martensitic steels irradiated in HFIR up to 20 dpa
Category: Fusion engineering/HFIRYear-Number㧦04-09 - No. 3
H. Tanigawa, M.A. Sokolov*, R.L.Klueh*, K. Shiba
JAEA, *ORNL.

DBTT , qC
qC

Tirrad.
300qqC
irrad. = 300qC

0

-100

-200

0

0.1

1

10

100

Irradiation damage (dpa)

Fig. 1. Irradiation damage dependence of the DBTT of
F82H-IEA irradiated at 300°C and 380°C. Data points
indicated by small squares were reported elsewhere [3].
15
0 dpa
5 dpa

USE, J

1020 dpa5
Grain size

3.3
6.5

F82H-IEA
F82H HT2

0
-150

-100

-50

0

50

100

150

DBTT, qC

Fig. 2. Effect of prior austenite grain size on Charpy
impact properties.
300
5dpa / 573K

250

F82H+2Ni

200'DBTT ,qC

Irradiation up to 11 dpa at temperatures below 400°C
indicated that the magnitude of the shift in ductile-brittle
transition temperature (DBTT) to a higher temperaturedepends on irradiation dose. This is important because
100°C is expected to be the lowest temperature of fusion
reactor blankets [1-3]. Current interest is to determine
whether or not there is a dose at which the change in
DBTT saturates, and to know the degradation level of
toughness at saturation. Additionally, the effect oftransmutation-formed helium on the mechanical properties,
especially fracture toughness, is one of the most important
issues that need to be understood for expected power plant
reactor application. The effects of irradiation up to 20 dpa
on the Charpy impact properties of reduced-activation
ferritic/martensitic steels (RAFs) were investigated.
The irradiation dose dependence of the shift in DBTT('DBTT) for F82H-IEA is summarized in Fig. 1.
Irradiation up to 5 dpa at 300°C shifted the DBTT up tonear room temperature, and there was no obvious
indication suggesting a saturation of the DBTT shift. On
the other hand, the DBTT was not further increased by anincrease in irradiation from 11 dpa [3] to 20 dpa at 380°C.
This result indicates the 'DBTT induced by irradiation
around 380°C was saturated at 11 dpa.
The effects of prior austenite grain size on DBTT shift
were investigated by comparing F82H-IEA (ASTM grain
size 3.3) to F82H-HT2 (ASTM grain size 6.5). The finegrain structure in F82H-HT2 was obtained byrenormalizing F82H-IEA using a lower austenitization
temperature (920°C). The results show that the DBTT ofboth unirradiated and irradiated HT2 are slightly (~20°C)
lower than for F82H-IEA, and the finer-grain F82H-HT2
has a higher USE than F82H-IEA. (see Fig. 2). From theseresults, it is concluded that F82H-HT2 benefited from thefine grain size after irradiation compared to F82H-IEA
steel.
The correlation between 'DBTT and yield stressincrease ('Vy) is shown in Fig. 3 for F82H-IEA, F82HHT2, F82H+2Ni, 9Cr-2WVTa and JLF-1. The three F82H
variants follow the same trend. Ni-doped specimens arealso on the same trend. From these data, the large 'DBTTof Ni-doped F82H could be explained as the effect ofradiation hardening, just as the other steels. The values for
9Cr-2WVTa and JLF-1 are slightly lower than the main
trend. The reason for this difference between F82H and thetwo 9Cr steels was not clarified in this study, and will be
investigated further in the future.

Tirrad.
irrad. = 380qC

100

150

F82H-IEA

100

F82H HT2

50

JLF-1

9Cr-2WVTa

0
0

200

400
'Vy, MPa

600

800

Fig. 3. Relation between DBTT shift and yield stressincrease.
1.
2.
3.

109

K. Shiba, M. Suzuki and A. Hishinuma, J. Nucl. Mater. 233-237(1996) 309
K. Shiba and A. Hishinuma, J. Nucl. Mater. 283-287 (2000) 474
R.L. Klueh, M.A. Sokolov, K. Shiba, Y. Miwa and J.P.
Robertson, J. Nucl. Mater. 283-287 (2000) 4784.

Heat Treatment Effect on Fracture Toughness of F82H Irradiated at HFIR
Category: Fusion engineering/HFIRYear-Number㧦04-09 - No. 4
N. Okubo, M.A. Sokolov*, H. Tanigawa, T. Hirose, S.
Jitsukawa, T. Sawai and R. E. Stoller*
JAEA, *ORNL.

Results of irradiation experiments on mechanicalproperties at temperatures from 250 to 500oC at damagelevels up to 20 dpa indicated that the irradiation effects
were in a manageable range. Improvements of postirradiation toughness and ductility by optimization andtightening of tempering condition are quite beneficial toexpand the service condition of RAF/M and seem todeliver more flexibility for DEMO design. The
methodology of improving post-irradiation toughness andductility is also expected to be applicable for other RAF/M
steels.

The reduced activation ferritic/martensitic (RAF/M)
steel F82H is recognized to be a leading candidate material
for in-vessel components in a future fusion DEMO reactor,
as well as that for ITER test blanket modules (TBM) in
Japan [1]. Examination of the neutron irradiation responseof RAF/M steels has been carried out mainly in DOEJAEA collaborative experiments using the High Flux
Isotope Reactor at Oak Ridge National Laboratory. F82H
is the reference heat for the collaborative experiments. The
results of recently completed post-irradiation examination
demonstrated a significant improvement in the irradiationinduced degradation of fracture toughness after optimizing
and tightening the heat treatment condition. The
degradation of fracture toughness was evaluated by theshift of ductile to brittle transition temperature (DBTTshift). The optimization and tightening of tempering
condition are also revealed to be effective for maintaining
post-irradiation ductility. DBTT-shift and reduction ofductility by irradiation have been recognized to be criticalissues for RAF/M steels; therefore, the beneficial effect of
the optimization of tempering condition may be extended
to the service conditions of RAF/M steels.
After irradiation, the DBTT is known to be dominatedby hardness or flow stress level. Some of the tensile resultsof irradiated weld joint specimens indicated that the postirradiation flow stress level might be reduced bymodification of tempering conditions [2]. Based on thisknowledge, ion and neutron irradiation experiments havebeen carried out to examine the dependence of postirradiation hardness and ductility on tempering conditions
using hardness and tensile specimens, respectively [3]. The
specimens were tempered between 700 and 800oC for 0.5
to 10 hrs before irradiation. Results showed that longer
tempering times are beneficial for reducing the postirradiation hardness. Miniaturized bend bar specimens(half size of 1/3-CVN specimen) with a fatigue pre-crack
were tempered at a higher temperature and/or for a longer
time. The specimens were irradiated to 20 dpa and tested
at several temperatures. Figure 1 shows the results. Data
points for IEA-F82H show the result for a reference
tempering condition of 750 oC for 1h. Data for a longer
tempering time (700oC for 10 hrs), noted as a “Mod1Series” clearly exhibit lower DBTT after irradiation. The
DBTTs are about 0 and 50oC for Mod1 and IEA,
respectively. The DBTT reduced by about 50oC. Althoughthe 20 dpa damage level is much less than the target of 100
dpa for DEMO, the tendency for the DBTT-shift tosaturate with increasing damage level suggests that thelarge improvement of irradiation performance of DBTT
would be maintained at higher damage levels.

IEA non irrad.

1/2(MPa m )300
IEA 18 dpa

1T-CT specimens

Mod1 18 dpa
Mod1 13 dpa

Toughness K

Jc

200

100

0
-200

-100

0

100

o

Temperature ( C)
Fig. 1. Temperature dependence of fracture toughness of
F82H specimens irradiated to 18 dpa
Results indicate
substantial reduction of the effect of radiation on fracture
toughness due to optimization/tightening of tempering
conditions. Miniaturized bend bar specimens were used.
Data shown in the circle were measured from large size
(1T-CT:1 inch thickness) specimens.

[1] A. Hishinuma, A. Kohyama, R. L. Klueh, et al., J. Nucl.
Mater. 258-263(1998)193.
[2] K. Shiba, R.L. Klueh, Y. Miwa, N. Igawa and J.P.
Robertson, DOE/ER-0313/28(2000)131.
[3] M. Ando, H. Tanigawa, E. Wakai, and R.E. Stoller, J.
Nucl. Mater. 386-388(2009)315.

110

Microstructure and hardness variation in a TIG weldment of irradiated F82H
Category: Fusion engineering/HFIRYear-Number㸸04-09 - No. 5
H. Tanigawa, M. Ando, T. Sawai, K. Shiba, .R.L.Klueh*,
R.E.Stoller*, N. Hashimoto**
JAEA, *ORNL, **Hokkaido Univ.

1200
Weld metalStress (MPa)1000

Base metal

800

Base metal
Unirrad.

600
400

HAZ

200
0
0

5

10

15

20

Strain (%)

Fig. 1. Tensile results of irradiated weldments andunirradiated base metal [1].

Heat affectedzone (HAZ)

HAZ

Base
metal

Weld metal

1

2

Transformation line

Transformation
line

3

5mm
Fusion Line

Fig. 2. Microstructure of TIG weldment and the definitionsof the different regions.

400

Vickers hardness Hv(500gf)

To validate the potential of reduced-activation
ferritic/martensitic steel (RAFM) as a structural material
for fusion power plants, the methodology for joining thesteel to form welds with adequate toughness before andafter irradiation must be developed. An irradiated tungsten
inert-gas (TIG) weld (weld metal, base metal and heataffected zone (HAZ)) of the IEA-modified F82H (F82HIEA) was investigated. Post-irradiation tensile tests and ahardness trace across the irradiated weld joint was
conducted to investigate the mechanical property changesof the TIG weld and to identify the location of the weldthat was involved with this low hardening.
Post-irradiation tensile tests of F82H-IEA TIG
weldment specimens were conducted. The results
indicated that the weld metal exhibited nearly the same
irradiation hardening as the base metal, but the HAZ
showed far less hardening than the base metal (Fig. 1).
The microstructure of the TIG weldment is shown in
Fig. 2. The microstructure consisted of 3 regions; i.e., weld
metal, HAZ, and base metal. The HAZ can be further
divided into 3 regions with obviously different
microstructures, and those regions are denoted with circled
numbers in Fig. 2. Here we call the boundary line between
region 1 and region 2 the transformation line, sincetheDJ transformation occurred during welding within theregion inside these lines. It should be noted that the
microstructure of the weld metal was rather fine except for
the last pass region, and the HAZ was wider than that of asingle-pass weldment, since a multi-pass TIG weld wasused.
The microhardness profiles across the weld joint are
shown in Fig. 3. Figure 3 (a) shows that minimum
hardness was obtained for both unirradiated and irradiatedspecimens in the “over-tempered region,” the region next
to the transformation line in region 1. On the other hand,both the minimum 'Hv and the minimum hardening ratio
were obtained in the “over-tempered region” (region 1)
and “fine-grain region” (region 2) located next to thetransformation line in region 2.
The tensile results suggest that a TIG weld joint of
F82H exhibited low irradiation hardening in a tensile test,compared to the base metal, and microhardness tests andmicrostructure observation revealed that the over-temperedzone in the HAZ exhibited similar good performance, i.e.,
low irradiation hardening. Hashimoto et.al. performed
transmission electron microscopy to analyze themicrostructure of these regions in the irradiated weldments[2]. No visible dislocation loops were observed in theover-tempered region and the fine-grained region. Small
dislocation loops were the main microstructural features in

F82H irradiated up to 5 dpa at 573K. This result indicatesthat more active point defect absorption and recombination took place in those regions, and they show
smaller irradiation hardening as a result.

(a)Hv (irradiated)

350
300
250

Base metal
Base metal200

Hv (unirradiated)

150
100
50
0
-10

-5

0

5

10

Distance from transformation line (mm)Fig. 3. The profile of hardness over irradiated andunirradiated weldments
1.

2.

111

K. Shiba, R.L. Klueh, Y. Miwa, N. Igawa, and J.P. Robertson,
Fusion materials semiannual progress report, DOE/ER-0313/28(2000) 131
N. Hashimoto, R.L. Klueh, M. Ando, H. Tanigawa, T. Sawai,, K.
Shiba,. Fusion Sci. and Tech. 44 (2003) 490

Irradiation effects on precipitation in reduced activation ferritic steels
the decrease of the M23C6 peaks of F82H-2Ni after
irradiation. It also should be noted that the spectra of allirradiated specimens tended to have broad and shallow
peaks with the median about 42 degrees.
These analyses suggest that irradiation caused (1)an increase of the amount of precipitates (mainly
M23C6), (2) an increase of Cr and decrease of W
contained in precipitates, and (3) the disappearance ofMX (TaC) in ORNL9Cr and JLF-1.

Category: Fusion engineering/HFIRYear-Number㧦04-09 - No. 6
H. Tanigawa, H. Sakasegawa, R.L.Klueh*, R.E.Stoller*
JAEA, *ORNLReduced-activation
ferritic/martensitic
steels(RAFs), such as F82H-IEA and its variants, ORNL9Cr2WVTa, JLF-1 and 2%Ni-doped F82H, show a varietyof changes in ductile-brittle transition temperature(DBTT) and yield stress after irradiation at 573K up to
5 dpa [1]. These differences could not be interpreted as
an effect of irradiation hardening caused by dislocation
loop formation.
The effects of irradiation on precipitation of RAFs
were investigated to determine how these effects might
affect the mechanical properties. The precipitation
behavior of the irradiated steels was examined byweight analysis, X-ray diffraction analysis and chemical
analysis on extraction residue.
The mass of extracted residue before and after
irradiation is shown in Fig. 1. Here the mass of residue
obtained with the coarse filter (column denoted ‘Large’)is interpreted as the value corresponding to the mass oflarge precipitates, and the difference of mass obtainedwith the fine filter and the coarse filter (column denoted‘Small’) is interpreted as that of the small precipitates.
These results indicate that during irradiation (1) the
mass of larger precipitates increased in F82H-IEA, JLF1, ORNL9Cr and F82H+2Ni, (2) small mass change
occurred in F82H HT2, (3) small precipitates
disappeared in JLF-1, and (4) the amount of small
precipitates doubled in F82H+2Ni.
The chemical composition of extracted residue wasanalyzed and the results show that (1) the precipitatesconsisted mainly of Cr, Fe, V and W, (2) Cr increased
after irradiation of each RAF except for JLF-1, and (3)W decreased after irradiation. It should be noted that (1)about half of the Ta was included in precipitates before
irradiation but dissolved after irradiation in JLF-1 and
ORNL9Cr, and (2) the amount of Ni in precipitatesfrom F82H+2Ni doubled after irradiation.
The XRD analysis of extracted residue (Fig. 2)
revealed that the majority of precipitates are M23C6 type(denoted with diamond mark) for all unirradiated andirradiated steels. Three distinctive peaks (denoted withtriangle) are observed on unirradiated JLF-1 and
ORNL9Cr, and those peaks are not detected onirradiated specimens. There is no exact match pattern
for those peaks, but the best match is for the TaC. This
supposition is quite reasonable as a high number densityof Ta- and V-rich precipitates is observed in thesesteels[2], and this agrees with the change of V and Ta
mass in precipitates. The reason for these peak offsetsfrom TaC could be that MX is a combination of V- andTa-rich carbides, nitrides, and carbonitrides (M: Ta, V,
Ti; X: C, N). The other feature obtained from Fig. 2 isFig. 1. Mass of residue of unirradiated and irradiatedRAFs extracted with coarse filter (Large) and fine filter(Large + Small).

Fig. 2. XRD peaks of extracted residue fromunirradiated and irradiated RAFs. Peaks marked withdiamonds correspond to the peaks from M23C6, andthose marked with triangles correspond to peaks from
MX (TaC).
1.
2.

112

H. Tanigawa, M. A. Sokolov, K. Shiba and R. L. Klueh:
Fusion Sci. Tech. 44 (2003) 206
H. Tanigawa, H. Sakasegawa, S. J. Zinkle, R. L. Klueh
and A. Kohyama: Fusion Materials Semiannual
Progress Report, (U.S. Dept. of Energy, Office of
Fusion Energy Science) DOE/ER-0313/35 (2003) pp.
30–32.

Creep behavior of RAFM irradiated at 300 and 500oC up to 5 dpa
A small piece was cut from the center of each
irradiated tube after diametral measurement.
Microstructural examination with FIBed samples andreplica films was carried out using TEM. For the 300oC
irradiation, the microstructure with hoop stress level of
250 MPa was similar to that in an unpressurized (zerostress) tube. Precipitates were observed along both lathand prior J-boundaries. Results of extraction replicas
indicated that finer spherical precipitates were observedat the highest hoop stress level. For 500oC irradiation,
large precipitates (>200nm) were observed along thegrain boundary at a hoop stress level 200MPa.
These results provide irradiation creep data for amaterials database for blanket structural design infusion reactors.

Category: Fusion engineering/HFIRYear-Number㧦99-04 - No. 7
M. Ando, M. Li*, M. L. Grossbeck*, L. T. Gibson*,
H. Tanigawa, K. Shiba, S. Jitsukawa,
Y. Kohno**, A. Kohyama**
JAEA, *ORNL, ** Muroran Institute of Technology

Fig. 1 Geometry of creep tube specimen
0.5

500oC
㪫㫆㫋㪸㫃 㪛㫀㪸㫄㪼㫅㫋㫉㪸㫃 㪪㫋㫉㪸㫀㫅㩿㩼㪀

Reduced activation ferritic/martensitic steels(RAFM) are the most promising candidates for blanket
structural materials for fusion reactors. Irradiation
creep has been recognized as one of the most important
properties for which engineering data is needed forblanket structural design. Several researchers havereported on irradiation creep and void swelling behavior
of austenitic stainless steels (Type 316 and PCA) andferritic steels (HT9 and 9Cr-1Mo) irradiated above
400oC[1-6]. In addition, some results of irradiation
creep experiments on RAFM above 390oC have beenreported by the Japan/US collaboration program forfusion materials [7].
For fusion reactors, it isanticipated that irradiation creep of RAFM at lower
temperatures could be also significant, and this would
have a large impact on the life expectancy of awater-cooled blanket system. However, irradiation
creep behavior of RAFM at temperatures below 400oC
has not yet been reported.
In the HFIR Phase IV program, pressurized creep
tube specimens were irradiated up to 5 dpa at 300 and
500oC and measured in ORNL Hot Laboratory.
The materials were the RAFM steels (F82H
prepared by JAERI and JLF-1 prepared by MEXT). The
tube specimens had dimensions of 4.57mm outside
diameter and 22.4mm length with a 0.2mm wall
thickness as shown in Fig. 1. End caps were electron
beam welded to the tube segments, and the specimens
were pressurized with high purity helium (99.999% He)
to obtain the desired hoop stresses at the irradiation
temperatures. The hoop stresses ranged from 0 to 400
MPa at the irradiation temperature. The diameter ofthese tubes was measured at the PNNL before
irradiation. Irradiation was performed in HFIR up to 5
dpa. The tubes were measured with a non-contacting
laser micrometer system.
Fig. 2 shows the relationship between the total
diametral strain and the hoop stress in RAFM irradiatedat 300 and 500oC. RAFM steels exhibit similar
irradiation creep behavior at 300oC up to 5 dpa. The
irradiation creep in these steels irradiated at 300oC is
almost linearly dependent on the hoop stress level
below 380MPa. Above 380MPa, creep strain tends toincrease strongly with increasing stress. For 500oC
irradiation, the irradiation creep of F82H is linearly
dependent on the hoop stress level below 180MPa. At
higher stress levels, the creep strain increased strongly
in these steels because thermal creep had also occurred
during irradiation.

0.4

300oC
0.3

0.2

0.1

0
0

100

200

300

400

500

HOOP STRESS (MP㪟㫆㫆㫇㩷㪪㫋㫉㪼㫊㫊㩷㩿㪞㪧㪸㪀

Fig. 2 Hoop stress dependence of irradiation creep at
300 and 500oC.
1.
2.
3.
4.
5.
6.

7.

113

A.F.Rowcliffe
andM.L.Grossbeck,
J.Nucl.Mater.
122-123(1984)181-190.
R. J. Puigh, J.Nucl.Mater. 141-143 (1986)954-959.
M.L.Grossbeck
andJ.A.Horak,
J.Nucl.Mater.
155-157(1988)1001-1005.
F.A.Garner
and
R.J.Puigh,
J.Nucl.Mater.179-181(1991)577-580.
M.B.Toloczko, F.A.Garner, C.R.Eiholzer, J.Nucl.Mater.
212-215(1994)604-607.
M. B. Toloczko, B. R. Grambau, F. A. Garner and K. Abe,
Proc. on Effects of Radiation on Materials, 20th Symp.,
ASTM STP 1405 (2001) 557.
A.Kohyama, Y.Kohno, K.Asakura, M.Yoshino, C.Namba,
C.R.Eiholzer, J.Nucl.Mater. 212-215(1994)751-754.

Plastic property and fracture condition of structural steels after irradiation
Category: Fusion engineering/HFIRYear-Number㧦04-09 - No. 8
K.Suzuki, T.Taguchi, N.Okubo and S.Jitsukawa, JAEA
At temperatures lower than 700K, irradiation often cause a severe
hardening to introduce a large change in stress-strain relation [1]. The
present authors, however, have indicated that the plastic property
before and after irradiation may be expressed by a simple equation of
V = A(H0 + Hp)n (1) where H0, Hp, A and n are an equivalent plasticstrain by irradiation hardening, plastic strain, strength coefficient andwork hardening exponent, respectively; A and n are the constants
without regard to the hardening level by irradiation. Similar
discussion has been also made in several researches [2-6]. The
present authors also indicated the relatively large margin to ductile
fracture was remained even after irradiation to some tens of dpas. In
case the equation (1) is applicable for the plastic property of irradiatedalloys, ductile fracture condition under tensile forces may be
estimated by e.g. Hill’s or Ghosh’s criteria [7, 8]. In other words,
irradiation hardened steel which has been recognized as a quasi-brittle
material is still ductile enough depending on the deformation mode.
In the present paper, plastic properties of irradiated steels are
introduced. Features of structural design criteria for intensely
irradiated steel component are also introduced.
A reduced activation ferritic steel F82H (0.1C-7.8Cr-2W-0.04Ta-Febal.) in normalized and tempered condition was used. Tensile
specimens of the steels were irradiated to 5 to 30 dpa at temperatures
between 250 to 400C in HFIR (some of the specimens were
irradiated in JMTR). Size of the gage region is 7.6mm long-1.5mm
wide-0.76mm-thickness. Specimens were also obtained from cold
worked plates. All the mechanical tests on irradiated specimens were
performed at room temperature in JMTR hot cell. The images ofgage region during deformation were recorded continuously.
Irradiation hardening caused to reduce tensile elongation (especially,
uniform elongation often reduced to zero) and to occur plastic
instability, as seen in the engineering stress-strain relation in theliterature [1]. The area at minimum cross section of the specimen
during the tensile test was evaluated from the image of the necked
region. From the area during testing and the engineering stress-strain
relation, an approximate true stress-true strain (Ts-s) curve has beenobtained (strain is in logarithmic strain). Results for the specimens
irradiated to 0, 5 and 20 dpa are shown in Fig. 1 (a). The curves for 5
and 20 dpa irradiated specimens were shifted along strain axis tooverlap the Ts-s curve for the unirrdiated specimen (see also Fig.
2(b)). The figure clearly shows that the curves overlap well with eachother, indicating that the equation (1) is applicable for the Ts-s relation
before and after irradiation without regard to irradiation damagelevels. The values of e0 applied for the curves of the specimens
irradiated to 5 and 20 dpa were of 0.33 and 0.7, respectively. Even
after irradiation to 20 dpa, residual ductility was about 30% of that
before irradiation. Indeed, as seen in Fig.2, effect of structural
discontinuity (circular hole at the center of the strip) was observed tobe relaxed during deformation before cracking had occurred [2];general yield occurred before the load attained maximum suggesting
considerable level of margin remained even for the specimen withdiscontinuity after irradiation and this was followed by neckdevelopment (images of the deformed specimens were also reported[2]). Moreover, bend testing on simulated irradiation hardened
specimen by cold working exhibited no apparent plastic instability.
As indicated above, the margin to fracture can be determined as afunction of deformation mode either by calculation or experiment.
This is also true for austenitics [4]. Structural design criteria assuring
the structural integrity of intensely irradiated steel component
delivering more freedom to designing comparing with current
methodology has began to be developed based on the analysis ofplastic and ductile fracture condition behavior after irradiation[2].

Fig. 1 (a) True stress-strain relations after 0, 5 and 20 dpa irradiation

Fig.1 (b) Illustration of the relation between True stress-strain relations of
unirradiated and irradiation hardened specimens.

General yield and elongation
Neck development

Fig. 2 Load-displacement curve of the irradiated plate tensile specimen with ahole (a discontinuity) at the center [2][1]S.Jitsukawa et al., Nuclear Fusion 49 (2009) 115006[2]K.Suzuki, Nucl. Eng. Design 240(2010)1290[3]T.Taguchi, et al., J. Nucl. Mater., 335(2004)457,[4]S.Jitsukawa, et. al., J. Nucl. Mater. 271&272(1999)162[5]R.J.DiMelfi et al., J. Nucl. Mater., 252 (1998) 171[6]T.S.Byun, K.Farrel, Acta Mater. 52(2004)1597[7]R.Hill, J. Mech. Phys. Solids 1 (1952) 19[8]A.K.Ghosh, in: D.P.Koinstein, N.M. Wang (Eds.), Mechanics ofsheet metal forming, Plenum, 1987, p.287

114

High Fluence Radiation Effects on Advanced SiC/SiC Composites
Category : Fusion Engineering / HFIR(No. 9)
Year Number: 99-09 – No. 9
Name: Y. Katoh, T. Nozawa*, L.L. Snead
Affiliation: ORNL, *JAEA

fibers, presenting river-like patterns originating fromindefinite mirrors around the fracture origins either on thesurface or at the fiber interior. No significant different in
the fracture surfaces, irradiated and unirradiated, wasobserved.
The swelling and the through-thickness thermal
conductivity, shown in Table 1, indicated the absence ofprogressive property evolution beyond a few dpa, proving
true saturation in key properties[2]. The electricalresistivity measurement revealed a transition from theunirradiated nearly temperature-independent conduction of
pyrocarbon interphase into a reduced, moderately
temperature-dependent conduction[1]. The effect ofirradiation on the composite electrical resistivity appeared
to be relatively minor. Overall, outstanding irradiation
resistance of the nuclear grade SiC/SiC composite toneutron irradiation to a dose exceeding 40 dpa attemperature of 800ºC was demonstrated.

Silicon carbide (SiC) has been studied for fission fuelapplications for several decades, and for the past two
decades as the base material for SiC fiber-reinforced SiCmatrix (SiC/SiC) composites, a potential high-temperature,
low-activation structural material for fusion energy. The
primary focus of study has been the development of aradiation stable material, given the poor as-irradiatedperformance of early materials. Over the past decadesignificant progress has been made towards this goal withthe development of what is now considered a nuclear grade
SiC/SiC composite composed of high purity, nearstoichiometric, and dense fibers and matrix. However,these composite materials have not been demonstrated toretain such fundamental properties as strength anddimensional stability under the high-dose irradiation typicalof power reactor blankets. In the DOE/JAEA fusionmaterials collaboration, the high-dose stability of thecurrent nuclear grade SiC/SiC composite was examined.
The material examined was chemically vaporinfiltrated (CVI) SiC matrix, Hi-Nicalon™ Type-S (HNLS)
SiC
fiber-reinforced
compositewithmultilayer
pyrocarbon/SiC interphase. Rectangular flexure beams
measuring 50.2 x 6.35 x 2.63 (mm) were irradiated in HFIR
to ~41 dpa at 800ºC. Post-irradiation mechanical properties
are briefly discussed in the present report, whereas the moredetailed report is found elsewhere.[1]The results of the post-irradiation examination aresummarized in Table 1. The composite material retained its
unirradiated ultimate and the proportional limit stresses
after irradiation. Moreover, no significant increase in data
scatter was observed for either property. Slight increases inboth the ultimate and proportional limit stresses may havebeen the case, but this increase is not statistically significant.
Examples of the recorded load – crosshead displacement
curves are presented in Fig. 1, showing no noticeable
difference between the unirradiated and irradiatedconditions. From these observations and accepted
composite theory it can be reasonably concluded that no
significant effect of irradiation on either the fracture energyof the matrix material, CVI SiC or the statistical strength
properties of the reinforcing fibers.
The fracture surfaces of the broken samples were
examined, and high magnification images of both thecomposite fracture surfaces and the fiber fracture surfaces
were compared for regions under tensile stress during
testing. The composite fracture surfaces were characterized
by generally very short yet finite fiber pull-out length anddebond/slide at the interface of the fiber and the interphase
whether or not the material has been irradiated. Both theunirradiated and irradiated fiber surfaces appear to be
typical of those observed for intact Hi-Nicalon™ Type-S

Table 1. Summary of unirradiated and irradiated properties.
Irradiation Temperature [ºC]Fast Fluence [dpa]Mass Density [g/cm3]
Swelling [%]RT Thermal Conductivity [W/m-K]
Young’s Modulus [GPa]Number of Flexural Tests
Proportional Limit Stress [MPa]Ultimate Stress [MPa]2D-HNLS/ ML/CVI-SiC
800
Unirr.
40.7
~2.4
~2.4
n/a
0.68 (0.01)
~9.8
~2.7
212 (10)210 (8)87317 (27)330 (20)444 (34)461 (48)600
UnirradiatedFlexural stress [MPa]50040.7 dpa at 800ºC

400
300
200
100
0
0

0.2

0.4

0.6

0.8
1
1.2
Flexural strain [%]

1.4

1.6

1.8

Fig. 1. Examples of four-point flexural load – crossheaddisplacement curves for unirradiated and irradiated HiNicalon™ Type S, CVI SiC matrix composites. Charts areoffset for visibility purpose.
[1] Y. Katoh, T. Nozawa, L.L. Snead, K. Ozawa, H.
Tanigawa, J. Nucl. Mater., (submitted).
[2] Y. Katoh, L.L. Snead, T. Nozawa, S. Kondo, J.T.
Busby, J. Nucl. Mater., (2010).

115

Modeling the Influence of Helium on Iron-based Alloys
Category : Fusion Engineering / HFIR
Year-Number : 2004-09 - No. 10
Name: R. E. Stoller, S. Jitsukawa*, D. M. Stewart
Affiliation: ORNL, *JAEA

In the investigation of helium bubbles, it was foundthat the helium atoms stand off a small distance from thesurface iron atoms, leaving a between the He and Fe matrix
atoms on the surface of the bubble [2]. The gap was large
enough that the He atoms rarely come close enough to aniron atom to invoke the 3-body component of the ORNL
Fe–He potential (range 2.2Å), so their interactions are
effectively described by the pair part of the potential. The
helium density oscillates enough to suggest a shell structure
to the arrangement of atoms, but not enough to suggest
solid helium. This agrees with predictions that the heliumin the bubble would not be solid. In a void, the surface
matrix atoms relax inwards slightly, reducing the volumeof the void. At higher temperatures, they move in more dueto the thermal expansion of the iron. Adding helium to thevoid pushes the atoms outwards, increasing the volume
again. The more helium added, the further the bubble
expands. There is a point where the forces balance and the
bubble is neither expanded nor contracted; the surface
atoms are at the same place as they would be in a perfectlattice. We use this point as our condition for equilibrium.
The equilibrium He/V ratio is temperature and size
dependant. In general, the equilibrium He/V ratio is lower
for higher temperatures and larger bubbles.
Figure 1 shows the dilation of a 2 nm diameter bubble
as a function of He/V ratio for different temperatures. The
equilibrium ratio for each temperature can be determinedby where it crosses the horizontal zero line. At 2 nm, thecurves for the different temperatures are close together andthe equilibrium He/V ratios lie in the range 0.4–0.55; forlarger bubbles, the curves spread out more (not shown).

In fusion applications, helium created bytransmutation plays an important role in the response of
reduced-activation ferritic/martensitic (RAFM) steels toneutron radiation damage. We have performed extensive
atomistic simulations using the ORNL 3-body Fe–He
interatomic potential [1] combined with three interatomic
potentials for the iron matrix. Interstitial helium is very
mobile and coalesces together to form clusters; the growthand mobility of these clusters has been investigated. Whenan interstitial He cluster reaches sufficient size, it punches
out an Fe interstitial, creating an immobile helium–vacancy
cluster. If more helium atoms join it, more Fe interstitials
can be created; the He–V defect is a nascent bubble. Thesemechanisms have been investigated together in simulations
that examine the nucleation of He defects. Mobileinterstitial He clusters and helium bubbles from 1 to 6 nm
in diameter were also simulated separately.
Helium-vacancy cluster growth and coalescence werestudied in molecular dynamics simulations to investigate
the nucleation of helium bubbles from interstitial helium
atoms using the Ackland iron and ORNL He–Fe potentials.
He interstitial cluster growth, coalescence and Frenkel paircreation were almost negligible at 200K but prevalent at all
higher temperatures. The temperature affected not just therate but also the nature of the defect creation process. The
higher the temperature, the faster He atoms and clusters
diffuse, which makes coalescence occur faster. This isbalanced by higher temperatures leading to small clusters
being broken up, delaying the creation of larger, stableclusters. The result is that that the cluster size distribution
is temperature dependant; higher temperatures lead to
fewer but larger clusters. Higher temperatures also increase
the number of Frenkel pairs likely to be emitted from alarger He–V cluster.
Diffusion rates for clusters of 1 to 6 interstitial helium
atoms were calculated for several combinations ofpotentials. Various combination of Fe and HE-Fe potentials
were compared. In general, larger clusters were found todiffuse slower, however there were significant differences
between the potentials. He-2 clusters tended to have asimilar or lower energy barrier than single interstitialhelium atoms but still diffuse slower due to a lower preexponential factor. The ORNL and Wilson potentials show
significantly higher barriers for He-3 and larger. The J–N
potential shows barriers of about 0.06eV for clusters of 1 to
4 interstitials, with the pre-exponential factor decreasing
with increasing cluster size. He-5 was found to have a(usually substantially) lower migration barrier than He-4
with all combinations of potentials used. A possible
explanation is that the tetrahedral arrangement of He-4 ismuch more stable due to its high symmetry that matches
the symmetry of the Fe matrix. He-5 configurations are farless symmetrical and, in some potentials, allow for rapid
1D diffusion.

2nm He bubble (339 vacancies)

Change in radius (lattice parameters)

0.020
0.015

100K
300K
450K
600K
900K

0.010
0.005
0.000
-0.005-0.010-0.015-0.020
0.0

0.1

0.2

0.3

0.4

0.5

0.6

He / V ratio

Fig. 1. Dilation of 2 nm bubbles as a function of He/V ratio
at different temperatures.
[1] R. E. Stoller, S. I. Golubov, P. J. Kamenski, T.
Seletskaia, and Yu. N. Osetsky, Phil. Mag. 90 (2010) 923.
[2] D. M. Stewart, Yu. N. Osetsky, R. E. Stoller, S. I.
Golubov, T. Seletskaia, and P. J. Kamenski, Phil. Mag. 90(2010) 935.

116

CHAPTER 8

Fusion Archives Activity

8.1 Objectives
History is said to be “an unending dialogue between the present and the past” (Edward H. Carr).
Even in the field of natural sciences, we should pay attention to history for looking at the present
state and the future. In particular, to learn lessons from the history of fusion is important formaking future plans of fusion research. Fusion archives play the role of providing “evidence” instudying this history. Moreover, big sciences like fusion research should fulfill their obligation ofsocial accountability. A formal organization in NIFS was established for fusion archives.
Archives in the US, in general, have been very advanced, which are expected to promote archivesof fusion researches. Moreover, fusion archives should cover not only the fusion research
activities of each country, but also the US-Japan collaborations, which occupy an important part of
the fusion activities in both countries.

8.2 Administration
A US-Japan workshop on fusion archives was planned and held in 2005 on the basis of activities inboth countries. Key persons were Prof. Mohamed Abdou in UCLA and Prof. Keisuke Matsuoka
in NIFS, respectively. At UCLA, there is active study of archives and Prof. Abdou, a fusion
scientist, has very much appreciated the importance of archives. At NIFS, Prof. Matsuoka had
been nominated as the director of the NIFS Fusion Science Archives (NIFS-FSA).

8.3 Summary of Activities
Fusion archives in universities in Japan originated in the move of Institute of Plasma Physics (IPP),
Nagoya University, to become part of the new National Institute for Fusion Science (NIFS) in Toki.
A vast amount of documents belonging to Prof. Kodi Husimi, the first director of IPP, wastransported from Nagoya to Toki in 1997, and their arrangement and registration was started on a
volunteer basis by retired professors of IPP and NIFS. In 1999, collaborative research at NIFS on
the fusion archives was initiated under the leadership of Prof. Sigeko Nisio of Nihon University.
A short time later, the Graduate University for
Advanced Studies (Sokendai), which consists ofseveral inter-university research institutes such as
NIFS, High Energy Accelerator Research
Organization (KEK), Institute of Molecular Science(IMS), and National Astronomical Observatory ofJapan (NAOJ), began to focus on archives in naturalsciences, especially in big sciences. Prof. Sharon
Traweek at UCLA played a role in starting thearchives activity of Sokendai.
Workshop at UCLA. From left, T.
On the basis of achievements at NIFS and the Tamano, A. Popescu, F. Chen, and Y.
Tomita.
approach by Prof. Hirotaka Sugawara of Sokendai, the117

NIFS Fusion Science Archives was established on January 1, 2005.
The NIFS Fusion Science Archives collaborates with universities where fusion research has been
done and with Sokendai. At PPPL, Ms. Adriana Popescu, the librarian, has worked to organize
and resister historical documents.
A US-Japan workshop on fusion archives was proposed in the same year that the NIFS Fusion
Science Archives was established. The workshop was held in the US in December 2005. The
workshop consisted of two parts: the first part was a workshop held at UCLA on December 12 and13, and the second part consisted of interviews with Dr. Kenneth M. Young and Dr. Shoichi
Yoshikawa on December 15 at PPPL. The speakers and their topics at the workshop in UCLA
were as follows.
“Welcome”
M. Abdou (UCLA)“Address (representing Japan)”
K. Matsuoka (NIFS)“Establishment of Fusion Science Archives and its activities”
K. Matsuoka“The Big Picture: Why Archives”
S. Traweek (UCLA)“History and Archives of Inter-University Research Institute: Related to Digital Contents in NIFS and
Sokendai”
N. Abe (Sokendai)“A History of progress in magnetic fusion energy research”
T. K. Fowler (UC Berkeley)“Archiving of nuclear fusion research in NIFS”
C. Namba (NIFS)“Archival study from chronological aspects”
K. Kimura (NIFS)“Role of Inter-University Institute in early days of nuclear fusion research in Japan”
H. Obayashi (NIFS)- Visit and Discussion at Center for Information as Evidence, UCLA –“The early days of Project Matterhorn”
F. F. Chen (UCLA)“Short history of Heliotron research and archiving activities in Kyoto University”
T. Mizuuchi (Kyoto Univ.)“Preservation and access of fusion research archives”
A. Popescu (PPPL)“International 4 year archive collaboration among physical scientists and social scientists”
S. Traweek“Complementary study of fusion science archives by means of oral history”
J. Fujita (NIFS)“Oral history projects with American research scientists”
M. Meldrum (UCLA)“Suggestions for Fusion Archives”
T. Tamano (GA)The topics from Japan included an overview of NIFS Fusion Science Archives activities, a history
of Heliotron machines, and digital archives necessary for cross-retrieval, chronological studies,and oral history. The US presentations covered the importance of archives and the early days of
US fusion research activities.
Both interviews at PPPL were conducted in English, following prepared questions.

118

In Dr.

Young’s interview, the topics were his research career before joining PPPL, the conversion of the C
Stellarator to the ST tokamak, diagnostics in TFTR, and comments on ITER. In the interview
with Dr. Yoshikawa, his involvement in Japan was the major topic due to his large impact on fusion
research in Japan. Transcriptions of both interviews have been completed.
The work on oral histories of prominent scientists has been continued. An interview with Dr.
Tihiro Ohkawa was carried out in Japanese at his home in November 2009 with detailed questions(this interview was supported by other funding). Topics in this interview covered his start offusion research, multi-pole experiments at GA, and his involvement in Japan research, since he had
had a significant influence on Japan, similar to Dr.Yoshikawa.

Interview with Dr. S. Yoshikawa on
December 15, 2005.

At PPPL on December 15. From left (front)
C. Namba, N. Abe, T. Mizuuchi, K. Kimura,(rear) M. Okabayashi, K. Matsuoka, Y.
Tomita, J. Fujita, H. Obayashi.

Interview with Dr. Ken M. Young on
Deember.15, 2005.

Interview with Dr. T. Ohkawa on Noember
18-19 2009. From left, K. Kimura, K.
Matsuoka, T. Ohkawa, T. Amemiya (Nihon
Univ.). Photo by C. Namba.

Since this workshop, the NIFS Fusion Science Archives has focused its efforts mainly on digitalarchives via collaborations with inter-university research institutes of Sokendai, especially the
National Institute of Japanese Literature (NIJL), KEK, and IMS, aiming to construct cross-retrieval
capability among database at these institutes, based on Encoded Archival Description (EAD). At
NIFS, the EAD system has been completed, as shown below, and the number of documents undercross-retrieval is increasing day by day.

119Subsequent visits (supported with other funding) to related institutes in the US—namely, CDL(California Digital Library), OAC (Online Archive of California), LBL Archives, SLAC andStanford Univ. Archives, UCLA (Information Studies Dept., University Archives, Digital Library
Program, Japanese Studies, East Asian Library, Oral History Research Center, Center for Society
and Genetics), NARA (National Archives and Records Administration) and LOC (Library ofCongress) provided much useful information about archives. Although the US is one of the mostadvanced countries on archives and a well-regarded cross-retrieval system has been established atsome organizations, e.g., LOC, there has been no construction of systematic archives on fusion
science. The ultimate goal of the US-Japan fusion science archives collaboration is to construct asystem for cross-retrieval of historical documents between Japan and US on the basis of EAD.
Further effort is needed to promote Fusion Science Archives, in anticipation of the construction offusion archives in US.

Cross-retrieval of “plasma” as an example. Database of materials provided by Prof. Yoshi-Hiko
Ichikawa and late Professors Tadashi Sekiguchi and Satio Hayakawa are retrieved on the screenof a computer.
Materials are arranged in the hierarchical structure that is characteristic ofEAD. Database of NIFS FSA, KEK, IMS are registered in the server of NIJL (National Instituteof Japanese Literature) that have constructed the cross-retrieval system of a vast amount of
database among institutes and libraries of humanities.

120

CHAPTER 9

Safety Monitoring Activities

9.1 Background and Objectives
In early 1992, there was an unfortunate event of concern in the US when a visiting Japanese
researcher was overcome by leaking nitrogen coolant gas. After this near-miss event, discussions
were held between Japan and US about conducting safety walkthroughs of fusion research facilities
and experiments in each country. As a result, the Japan-US Safety Monitoring Joint Working
Group (JWG) was established to work on understanding and addressing the various issues
regarding safety in inter-institutional collaborations, to examine these issues, to develop methods ofresolving them, and to make a set of recommendations directed to the governmental andoperational institutions of both parties. The activities of the JWG at fusion laboratories provide foran excellent exchange of information and perspective resulting in increased attention toward
personnel safety with specific attention to visiting collaborators at the national institutes anduniversities of both countries.
The purpose of the site visits by the JWG is to evaluate the programmatic aspects of environmental,
safety and health (ES&H) programs at fusion research facilities informally by touring laboratory
areas and meeting with researchers and safety professionals. Based on these interactions, the JWG
members have been able to share information and provide suggestions in an effort to reduce thelikelihood of bodily injury and/or property damage. The JWG encourages that good approaches andpractices developed at a certain institution be utilized to improve ES&H programs at otherinstitutions, and to provide guidance for necessary safety orientation programs for foreign
collaborators.
JWG site visits since FuY1995 (FuY coincides with Japanese fiscal year, and FuY corresponds toApril 1995 to March 1996) are summarized in Appendix B.2. Activities during the last 10 years are
summarized in the next sub-section. The JWG toured US laboratories and Japanese laboratories
alternately every two years during this period. Detailed reports of the JWG site visits are available
at http://www.pppl.gov/esh.cfm.

9.2 Summary of JWG Activities
9th JWG (J to US: March 18-22, 2002)
The Japanese delegation was particularly impressed by the commitment to safety by the laboratory
management. At most institutions, the EHS/ESH manager reports directly to the director of thelaboratory. Integrated Safety Management (ISM) is practiced at all institutions visited. DOE
provides the basic guidelines of ISM, but its implementation is tailored to suit specific needs ofeach institution. Each institution has a comprehensive training program, which has been useful inraising awareness of hazards and reducing the number of accidents/incidents. At many institutions
EHS/ESH related information is readily available.
In Japan, the JCO accident in Tokai has prompted reexamination of the safety program, and many121

changes have been made, but there is a need to update English versions of the Safety Manuals. This
tour included visits to smaller, university-scale labs to learn how their safety programs are
implemented. It was useful to hear about recent accidents/near-misses and what kinds of countermeasures were implemented.
10th JWG (US to J: February 16-25, 2004)
The US delegation was impressed with nearly all the labs’ progress and attention to the items
identified in the 1999 safety tour. During each site visit, an overview of the activities in the lab andthe overall safety program that was active in the lab were provided, followed by a tour of the labs
and associated facilities. After the tour of each lab, findings were shared with the Management andStaff in a closeout meeting, providing immediate feedback to the staff regarding issues that wereidentified. Many times during our tour, issues that were identified in the labs were immediately
corrected by tour participants or by individuals working in the lab. This action shows a proactive
attitude towards safety and is greatly appreciated.
Gas bottles need to be secured when in use. A gas bottle on a cart with a regulator installed is notconsidered secured. Electrical cords need to be of the industrial grade type which includes twolayers of insulation and not just one. The use of “ground pin bypass units” should be reviewed ineach lab and eliminated wherever possible. When a piece of equipment is manufactured with aground pin it should always be used for safety reasons.
It was anticipated that new safety rules will come into effect in April 2004 when the national
universities will be given increased safety regulations by the Ministry of Health, Labor, andWelfare. This new overview agency may help in providing guidance to the universities and can belooked at as a positive step toward a safer laboratory environment.
Most of the facilities visited were either maintaining a high level of safety or had shown
improvement in safety. Some professors stated that this improvement was created by two reasons,namely, our visits that gave them some guidance and the new rulemaking for university safety thatsoon takes effect. Only in one experiment did it appear that safety had decreased and immediate
attention should be placed on the serious safety items that were identified. The universities havecost constraints, so focusing on means to increase safety without incurring high costs is needed.
Using daily safety checklists before experiment operation, appointing a key person of theexperiment day to track safety issues, once-a-month cleanup days, and using pictogram warning
signs are all low cost means to achieve safety.
11th JWG (J to US: February 22-27, 2006)
This was the first time that representatives of inertial confinement fusion (Dr. Norimatsu) andfusion technology (Dr. Kohyama) participated in this activity. The Japanese delegation noted
substantial improvements in safety records since the last visit. At most institutions, ES&H policies
are based on the concept of Integrated Safety Management (ISM). DOE provides the basic
guidelines of ISM, but its implementation is tailored to suit the specific needs of each institution.
Each institution has a comprehensive training program which has been useful in raising theawareness of hazards and reducing the number of accidents/incidents. At many institutions,information related to ES&H is readily available electronically. The overall evaluation of the 2006122

site visits by the JWG is highly satisfactory, especially from the viewpoint of mutual understandingof differences in safety culture between the two countries. At institutes with many visiting
scientists or workers from outside, it is extremely important for everyone to have enoughknowledge of safety.
12th JWG (US to J: March 10-21, 2008)
Overall impressions of the labs and universities were very good. A major change since the previous
U.S. visit in February 2004 is that the major universities are now subject to Japan national rules foroccupational and industrial safety. Some of the professors stated that compliance with some of thenational laws and rules was expensive, but overall we noted the facilities were cleaner, lesscluttered, and tools were better organized. There was better attention to gas cylinder safety, more
safety signs were in use, and more attention to general industrial safety than in past visits. As
always, the facilities with larger annual operating budgets tend to have more safety provisions. It isa well known, but not quantified, safety principle that well-run, safe facilities are cleaner, moreproductive, and more efficient than facilities that do not practice safety.
There were many port covers and flanged openings at all of the facilities we visited, but few were
designated or labeled as confined spaces, and several facilities did not have a formal program forpersonnel entry into these spaces. Confined spaces may be encountered in virtually any occupation;
therefore, their recognition is the first step in preventing fatalities. Since deaths in confined spaces
often occur because the atmosphere is oxygen-deficient, toxic or combustible, confined spaces that
contain or have the potential to contain a serious atmospheric hazard should be classified as
Permit-required confined spaces and should be tested prior to entry and continually monitored. The
information source for the U.S. Occupational Safety and Health Administration (OSHA)
regulations with regard to confined spaces was provided.
Information in regard to the U.S. fall protection programs was also provided. In the US, all fall
protection products fit into four functional categories: 1. Fall Arrest, 2. Positioning, 3. Suspension,
4. Retrieval. A fall arrest system is required if any risk exists that a worker may fall from anelevated position. As a general rule, the fall arrest system should be used anytime a working heightof six feet or more is reached. A full-body harness with a shock-absorbing lanyard or a retractable
lifeline is the only product recommended. A full-body harness distributes the forces throughout thebody, and the shock-absorbing lanyard decreases the total fall arresting forces. A positioning
system holds the worker in place while keeping his/her hands free to work. Whenever the worker
leans back, the system is activated. However, the personal positioning system is not specificallydesigned for fall arrest purposes. A suspension system lowers and supports the worker whileallowing a hands-free work environment, and is widely used in window washing and painting
industries. Retrieval Preplanning for retrieval in the event of a fall should be taken into
consideration when developing a proactive fall management program.
The US visitors also noted that there have been several new machines built and operated since the2004 visit. These new machines indicate not only a healthy research program but also the need tocontinue performing these safety walkthrough tours.
13th JWG (J to US: Feb. 22-25, 2010)123

13th JWG
(J to US:Feb. 22-25,
2010) of NIFS, Associate Professor Seki of NIFS, and Dr.
Threemembers(Professor
Nishimura
Sukegawaof JAEA)of the Nishimura
Japanese delegation
for the firsttime
the Japan-US
Three members(Professor
of NIFS,participated
Associate ProfessorSekiof inNIFS,
and Dr.
SafetyMonitoring
Joint
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The
Japanesedelegation
was
greatly
impressedby high
Sukegawa of JAEA) of the Japanese delegation participated for the first time in the Japan-US
attention
to the ES&H
establishedAt mostinstitutions,
ES&H policies
Safety Monitoring
JointandWorking
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Theorganization.
Japanese delegation
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greatly impressedby higharebasedtoonthethe
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who anddoessuitable
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oftakenthe 2009
site visits forby theJWG whois highly
In particular,
entrance areautomaticallya persondoessatisfactory.
not take necessary
lectures.understanding
The overallofdifferencesin safety
culturebetweentwois countries
and betweenIn
theparticular,different states
in USAevaluationof the2009 site
visitsby the the
JWG
highly satisfactory.
understandingisof note.
Atculture
institutes
with themany
scientists
or workers
from statesoutside,it isof worthy
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betweentwovisiting
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and between
the different
in USA
extremelyfor institutes
everyone withto haveenoughknowledge
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to have enoughknowledge
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standards
in various
visitors wereable tocountries.
recognize the importance of safety education based on a difference in safety
standards in various countries.
Publications
Publications
R. L. Savercool and L. C. Cadwallader, “Activities of the U.S.-Japan Safety Monitor Joint Working
Group,”
Fusion ScienceandTechnology,“Activities
47 (2005) of
974-978.
R. L. Savercool
and L. C.
Cadwallader,
the U.S.-Japan Safety Monitor Joint Working
Group,” Fusion Science and Technology, 47 (2005) 974-978.
L. C. Cadwallader, “Compressed Gas Safety for Experimental Fusion Facilities,” Fusion Scienceand
47 (2005)
989-994.
L. C.Technology,
Cadwallader,“Compressed
Gas Safety for Experimental Fusion Facilities,” Fusion Scienceand Technology, 47 (2005) 989-994.
K. R. Rule, L. C. Cadwallader, T. Norimatsu, Y. Takase, M. Sato, O. Kaneko, and R. Savercool,“Elements
and Safe
Fusion ExperimentOperations,”
Proceedings
the 23rd
K. R. Rule,ofL. Successful
C. Cadwallader,
T. Norimatsu,
Y. Takase, M.
Sato, O. Kaneko,
and R.ofSavercool,
Symposium
Engineering,
1-5, 2009,
San Diego,
CA, IEEEProceedings(2009).
“Elements onof Fusion
Successful
and SafeJune
FusionExperimentOperations,”of the 23rd
Symposium on Fusion Engineering, June 1-5, 2009, San Diego, CA, IEEE (2009).

124Appendices
Appendix A
List of Published Papers
Appendix B
Statistics and Related Documents

Appendix A
List of Published Papers

CHAPTER2FTPC
2.4.1SuperconductingMagnets
1䠊JournalPaper
No

Year

Authors

Title of Paper

JournalVol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

2002

N. Yanagi, J. Morikawa, T.
Engineering Research and Development ofMito, Y. Ogawa, S.
Magnetically Levitated High-Temperature
Hamaguchi, H. Chikaraishi, M.
Superconducting Coil System for Mini-RT
Iwakuma, T. Uede, I. Itoh, S.
Project
Nose, and S. Fukui

IEEE Trans. Appl. Supercond

12 (2002) 948-951

2001-FT1-2

2003

Y. Ogawa, J. Morikawa, T.
Mito, N. Yanagi, M. Iwakuma, Construction and Operation of an Internal
H. Nihei, K. Ohkuni, D. Hori, S. Coil Device with a High Temperature
Yamakoshi, I. Itoh, S. Nose,
Superconductor
and T. Uede

IEEE Trans. Appl. Supercond

13 (2003) 643-644

2001-FT1-2

2003

T. Mito, N. Yanagi, Y.
Hishinuma, Y. Ogawa, J.
Morikawa, K. Ohkuni, M.
Engineering Design of the Mini-RT Device
Iwakuma, T. Uede, S. Nose, I.
Itoh and S. Fukui

IEEE Trans. Appl. Supercond

13 (2003) 1500-1503

2001-FT1-2

2003

N. Yanagi, T. Mito, Y.
Hishinuma, Y. Ogawa, J.
Morokawa, K. Ohkuni, M.
Iwakuma, T. Uede, S. Nose,and I. Itoh

Excitation Test Results of the HTS Floating
Coil for the Mini-RT ProjectIEEE Trans. Appl. Supercond

13 (2003) 1504-1507

2001-FT1-2

5

2004

N. Yanagi, T. Mito, J.
Morikawa, Y. Ogawa, K.
Ohkuni, D. Hori, S.
Yamakoshi, M. Iwakuma, T.
Uede, I. Itoh, M. Fukagawa,and S. Fukui

Experiments of the HTS Floating Coil System
IEEE Trans. Appl. Supercondin the Mini-RT Project14 (2004) 1539-1542

2001-FT1-2

6

2004

Experimental Apparatus for Measuring the
T. Hemmi, K. Takahata, T.
Characteristics of HTS Coils underMito, A. Iwamoto, H. Tamura,Controllable Magnetic Field, Orientation
and N. Yanagi
and Temparature

IEEE Trans. Appl. Supercond

14 (2004) 1806-1809

2001-FT1-2

7

2005

N. Yanagi, T. Mito, T. Hemmi,
Effective Resistance of the HTS Floating CoilIEEE Trans. Appl. Supercond
K. Seo, J. Morikawa, Y.
of the Mini-RT Project
Ogawa, and M. Iwakuma

15 (2005) 1399-1402

2004-FT1-2

8

2005

T. Hemmi, N. Yanagi, K. Seo,
Experimental Evaluation of Loss Generation
R.Maekawa, K. Takahata, andIEEE Trans. Appl. Supercond
in HTS Coils Under Various Conditions
T. Mito15 (2005) 1711-1714

2004-FT1-2

9

2006

Y. Ogawa, J. Morikawa, T.
Mito, N. Yanagi, and M.
Iwakuma

Application of high-temperature
superconducting coil for internal ring
devices

Fusion Engineering and Design

81 (2006) 2361-2369

2005-FT1-1

10

2006

T. Mito, A. Sagara, S.
Imagawa, S. Yamada, K.
Takahata, N. Yanagi, H.
Chikaraishi, R. Maekawa, A.
Iwamoto, S. Hamaguchi, M.
Sato, N. Noda, K. Yamauchi,
A. Komori, and O. Motojima

Applied superconductivity and cryogenic
research activities in NIFS

Fusion Engineering and Design

81 (2006) 2389-2400

2005-FT1-1

11

2006

T. Hemmi, N. Yanagi, G.
Bansal, K. Seo, K. Takahata,
and T. Mito

Electromagnetic behavior of HTS coils in
persistent current operations

Fusion Engineering and Design

81 (2006) 2463-2466

2005-FT1-1

Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

180 (2001) 66-71

2001
MM-32

307-311 (2002) 521-526

2002
MM-27
MM-28

1

2

3

4

2.4.2StructuralMaterials
1䠊JournalPaper
No

Year

1

2001

K. Morishita, T. Diaz de la
Rubia and A. Kimura

Mobility of Self-interstitial Atom Clusters in Nuclear Instruments and Methods
Vanadium, Tantalum and Copperin Physical Research B

2002

A. Kimura, R. Kasada, K.
Morishita, R. Sugano, A.
Hasegawa, K. Abe, T.
Yamamoto, H. Matsui, N.
Yoshida, B.D. Wirth and T.D.
de la Rubia

High Resistance to Helium Embrittlement in
J. Nucl. Mater
Reduced Activation Martensitic Steels

2

Authors

Title of Paper

Journal

A−1

3

2002

S. Jitsukawa, M. Tamura, B.
van der Schaaf, R.L. Kleuh, A.
Alamo, C. Petersen, M.
Development of an Extensive Database of
Schirra, P Spaetig, G.R.
Mechanical and Physical Properties for
Odette, A.A. Tavassoli, K.
Reduced-Activation Martensitic Steel F82H
Shiba, A. Kohyama and A.
Kimura4

2002

R.L. Klueh, D.S. Gelles, S.
Jitsukawa, A. Kimura, G.R.
Ferritic/Martensitic Steels – Overview ofOdette, B. van der Schaaf and Recent Results
M. Victoria

J. Nucl. Mater

307-311 (2002) 455-465

2002
MM-27
MM-28

5

2004

D. C. Dube, P.D. Ramesh, J.
Cheng, M.T. Lanagan, D.
Agrawal and R. Roy

Experimental evidence of redistribution offields during processing in a high-power
microwave cavity

Appl. Phys. Lett.

85 (16) (2004) 3632-3624

2004-FT2-1

6

2004

S. Jitsukawa, A. Kimura, A.
Kohyama, R.L. Klueh, A.A.
Tavassoli, B. van der Schaaf,
G.R. Odette, J.W. Rensman,
M. Victoria and C. Petersen

Recent Results of the Reduced Activation
Ferritic/Martensitic Steel Development

J. Nucl. Mater

329-333 (2004) 39-46

2004
FT2-2

7

2005

S.A. Maloy, M.R. James, T.J.
Romero, M.B. Toloczko, R.J.
Kurtz and A. Kimura

Tensile properties of the NLF reduced
activation ferritic/martensitic steels after
irradiation in a fast reactor spectrum to a
maximum dose of 67 dpa

J. Nucl. Mater.

341 (2005) 141-147

2004
FT2-2

8

2007

Kotaro ISHIZAKI, Kazuhiro
NAGATA

Selectivity of Microwave Energy
Consumption in the Reduction of Fe3O4
with Carbon Black in Mixed Powder

ISIJ.

47 (2007) 811-816

2004-FT2-1,
2005-FT2-1,
2006-FT2-1,
2007-FT2-1

9

2008

V.D. Buchelnikov, D. V.
Heating of metallic powders by
Louzguine-Luzgin, G.Q. Xie, S.
microwaves: Experiment and theory
Li, N. Yoshikawa, M.Sato

J. Appl. Phys.

104 (2008) 113505

2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

10

2008

A.P. Anzulevich, I.V. Bychkov, Numerical study of microwave heating ofand A.Inoue
micrometer size metal particles

ISIJ (Iron and Steel Institute ofJapan)48 (2008) 681-684

2004-FT2-1,
2005-FT2-1,
2006-FT2-1,
2007-FT2-1

11

2008

H.Tanigawa, T.Hirose,
K.Shiba, R.Kasada, E.Wakai,
H.Serizawa, Y.Kawahito,
S.Jitsukawa, A.Kimura,
Y.Kohno, A.Kohyama,
S.Katayama, H.Mori,
K.Nishimoto, R.L.Klueh,
M.A.Sokolov, R.E.Stoller,
S.J.Zinkle

Technical issues of reduced activation
ferritic/martensitic steels for fabrication of
ITER test blanket modules

Fusion Engineering and Design

83 䠄2008䠅 1471-1476

2008
MM- 19122009

M. Tanaka, H. Kono, and K.
Maruyama

Selective heating mechanism of magnetic
Phys. Rev. B
metal oxides by a microwave magnetic field

79 (2009) 10442

2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

13

2009

Handling Technology of Mega-Watt
M.Ignatenko, M.Tanaka, andMillimeter-Waves For Optimized Heating of Jpn.J.Appl.Phys.
M.SatoFusion Plasmas

48 (2009) 067001

2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

14

2009

A. Matsubara, S. Takayama,
S. Okajima and M. Sato42 (2008 ) 4

2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

Conference Name

Month Date, Year, Place, CountryYear-Category-No.

J. Nucl. Mater

307-311 (2002) 179-186

2002
MM-27
MM-28

Evolution of the near-UV emission spectrum
J. Microwave Power
associated with the reduction process in theElectromagnetic Energy
microwave iron making

2䠊ConferencePaper
No

Year

1

2001

K. Morishita, R. Sugano, B.D.
Atomistic Simulation Study of Helium
Wirth, H. Iwakiri, T. Diaz de la
Behavior in Iron and Helium Desorption
Rubia, N. Yoshida and A.
Experiments
KimuraProc. of the CARET Symposium on
Advanced Research of Energy
Technology

March 18-16,2001, Sapporo, Japan

2001-MM-32

2

2004

M. Sato, S.Takayama

Microwave Sintering Technology in Japan

4th International Congress on
Microwave and Rf Applications

Nov.7-11, Texas Austin

2004-FT2-1,

3

2008

M. Sato, K. Nagata, A.
Matsubara, S.Takayama

Greener Steel Making Process by
Microwave Irradiation with Discharges

June 15-19 (2008) Karlsruhe,
Germany

2004-FT2-1,
2005-FT2-1,
2006-FT2-1,
2007-FT2-1

2009

M. Sato, N. Nishi, M. Tanaka,
A.Matsubara, S Takayama, H. Formation of Nano-Domains by Microscopic
Ist Global Cong MW Energy
Fukushima, M. Ignatenko,
Thermal Non-Equilibrium Generated in GHz
Applications, August 2008, Japan
Rustum Roy, Dinesh Agrawal, High Frequency Microwave Field
J. Fukusima

Aug.7-10,2008, Otsu, Japan

2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

4Authors

Title of PaperICPOS2008

A−2

5

2009

M.SatoMicrowave Excited Non-equilibrium
Reaction Field that Brings Revolution to Key
IEICE 䠩䠳䠡2009
Industries of 21 Century䡡IEICE 䠩䠳䠡2009䡡
2009

6

2009

M.Tanaka, H.Kono,
K.Maruyama, and
M.Ignatenko

2009

K.Nagata, K. Ishizaki,
M.Kanazawa, T. Hayashi,
M.Sato, A.Matsubara,
S.Takayama, O.Motojima,
D.Agrawal, R. Roy

7

Nov. 16-18, 2009, Yokohama, Japan

2004-FT2-1,
2005-FT2-1,
2006-FT2-1,
2007-FT2-1

Classical and Quantum
12th AMPERE International
Mechanical Theories of Microwave Heating
Conference 2009of Magnetic Materials

Sep 16-21, Karlsruhe, Germany(AMPERE Europe,The 2009 Best
Paper Award )2004-FT2-1,2-3,
2005-FT2-1,2-3,
2006-FT2-1,2-2,
2007-FT2-1,2-2

A Concept of Microwave Furnace for Steel
Making in Industry Scale

Sep 16-21, Karlsruhe, Germany

2004-FT2-1,
2005-FT2-1,
2006-FT2-1,
2007-FT2-1

Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

12th AMPERE International
Conference 2009

2.4.3PlasmaHeatingRelatedTechnologies
1䠊JournalPaper
No

Year

1

2001

M. A. Shapiro, T. S. Chu, D. R.
Design of correcting mirrors for a gyrotron
Denison, M. Sato, T.
used at Large Helical Device
Shimozuma, R. J. Temkin

Fusion Engineering and Design

53 (2001) 537–544

2005-FT3-5
2003-FT3-7
2000-FT3-3

2

2002

N. Takeuchi, R. Kumazawa, K. The radio frequency charactertistics of the
Saito, T. Watari, T. Seki, et al. combline antenna

Journal of Plasma Fusion Research
SERIES

5 (2002) 314-317

2002-FT3-2

3

2004

N. Takeuchi, T. Seki, Y. Torii,
K. Saito, T. Watari, et al.

Variation of N// and its effect on fast wave
electron heating on LHD

Journal of Plasma Fusion Research
SERIES

6 (2004) 642-646

2003-FT3-3

4

2004

Y. Takase, C.P. Moeller, T.
Seki, N. Takeuchi, T. Watari,
et al.

Development of a fishbone travelling wave
antenna for LHD

Nuclear Fusion

44 (2004) 296-302

2003-FT3-3

5

2005

N. Takeuchi, T. Seki, K. Saito, Studies of the electrical properties of theT. Watari, R. Kumazawa, et al. LHD combline antenna

Fusion Science and Technology

48 (2005) 1267-1284

2003-FT3-3

2005

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Ito, T. Alignment Method of ECH Transmission
Notake, S. Kubo, Y.
Lines Based on the Moment and Phase
Yoshimura, S. Kobayashi, Y.
Retrieval Method Using IR Images
Mizuno, Y. Takita, K. Ohkubo

J. Plasma Fusion Res.

81 (2005) 191 - 196

2005-FT3-5
2003-FT3-7
2000-FT3-3

2009

T. Shimozuma, S. Kubo, Y.
Yoshimura H. Igami, H.
Takahashi, Y. Takita, S.
Kobayashi, S. Ito, Y. Mizuno, Handling Technology of Mega-Watt
Journal of Microwave Power &H. Idei, T. Notake, M. A.
Millimeter-Waves For Optimized Heating ofElectromagnetic Energy
Shapir, R. J. Temkin, F. Felici. Fusion Plasmas
T. Goodman, O. Sauter, R.
Minami, T. Kariya, T. Imai andT. Mutoh43 (2009) 60-70

2007-FT3-6
2008-FT3-1
2009-FT3-3

2010

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Kubo,
Mode-Content Analysis and Field
H. Igami, Y. Yoshimura, H.
Reconstruction of Propagating Waves in
Takahashi, S. Ito, S.
CorrugatedWaveguides of an ECH System
Kobayashi, Y. Mizuno, Y.
Takita and T. Mutoh

5 (2010) S1029-1-5

2007-FT3-6
2008-FT3-1
2009-FT3-3

Month Date, Year, Place, CountryYear-Category-No.

6

7

8

Authors

Title of Paper

JournalPlasma and Fusion Research

2䠊ConferencePaper
No

Year

Authors

Title of Paper

1

2001

N. Takeuchi, K. Saito, R.
Kumazawa, T. Watari, et al.

The Radio Frequency Characteristics of the
Combline antenna

The 12th International Toki
Conference

Dec. 11-14, 2001, Toki, Japan

2002-FT3-2

2

2003

N. Takeuchi, T. Seki, Y. Torii,
K. Saito, et al.

Ray tracing calculation for the fast wave
electron heating on LHD

The 13th International Toki
Conference

Dec. 9-12, 2003, Toki, Japan

2003-FT3-3

3

2003

T. Shimozuma, H. Idei, M. A.
Shapiro, T. Notake, S. Ito, S.
Kubo, R. J. Temkin and K.
OhkuboAlignment Method of Transmission Lines
Based on the Moment and Phase Retrieval
Method Using IR images

EU-US-JA RF heating technology
workshop 2003

Sept. 25-26, Tokai, Ibaragi, Japan

2000-FT3-3
2005-FT3-5

2004

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Ito, T.
Alignment Method of Transmission Lines
Notake, S. Kubo, Y.
Based on the Moment and Phase Retrieval
Yoshimura, S. Kobayashi, Y.
Method Using IR images
Mizuno, Y. Takita and K.
Ohkubo15th Nucler Fusion Energy
Conference

June 17-18,2004, Sendai, Japan

2003-FT3-7
2000-FT3-3

4

Conference Name

A−3

5

2005

T. Shimozuma, S. Kubo, Y.
Yoshimura, H. Igami, H. Idei,
T. Notake, S. Ito, S. Kobayashi, Improvement of ECH System for HighY. Mizuno, Y. Takita, M. A.
Performance Experiments in LHD
Shapiro, R. J. Temkin, K.
Ohkubo and T. Mutoh

6

2007

T. Oosako, et al.

2007

T. Shimozuma, H. Idei,
Efficiency improvement in long-distance
M.Shapiro, R.J.Temkin, S.
transmission of high-power millimeter
Kubo, Y. Yoshimura, H. Igami,
waves by propagating mode analysis in
T. Notake, S. Ito, S. Kobayashi.
corrugated waveguides
Y. Mizuno, Y. Takita, T. Mutoh

2008

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Kubo,
Propagating Mode Contents in the
H. Igami, Y. Yoshimura, H.
Corrugated Waveguides of ECH System for
Takahashi, S. Ito, S.
Precise Alignment
Kobayashi, Y. Mizuno, Y.
Takita and T. Mutoh

2008

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Kubo,
In-situ mode analysis of high power
Y. Yoshimura, H. Igami, H.
millimeter-waves propagating in the
Takahashi, S. Ito, S.
corrugated waveguide
Kobayashi, Y. Mizuno, Y.
Takita and T. Mutoh

2008

T. Shimozuma, H. Idei, M. A.
Shapiro, R. J. Temkin, S. Kubo, Propagating Mode Analysis and Field
Y. Yoshimura, H. Igami, H.
Reconstruction in the Corrugated
Takahashi, T. Notake, S. Ito, S. Waveguides of a High Power Electron
Kobayashi, Y. Mizuno, Y.
Cyclotron Heating System
Takita and T. Mutoh

2008

T. Shimozuma, S. Kubo, Y.
Yoshimura, H. Igami, H.
Takahashi, Y. Takita, S.
Kobayashi, S. Ito, Y. Mizuno, Recent Studies toward Improvement of
H. Idei, T. Notake, M. A.
Total ECH Efficiency in LHD
Shapiro, R. J. Temkin, F. Felici,
T. Goodman, O. Sauter, and T.
Mutoh

12

2008

T. Shimozuma, S. Kubo, Y.
Yoshimura, H. Igami, H.
Takahashi, Y. Takita, S.
Kobayashi, S. Ito, Y. Mizuno, HANDLING TECHNOLOGY OF MEGA-WATT
H. Idei, T. Notake, M. A.
MILLIMETER-WAVES FOR OPTIMIZEDShapiro, R. J. Temkin, F. Felici, HEATING OF FUSION PLASMAS
T. Goodman, O. Sauter, R.
Minami, T. Kariya, T. Imai andT. Mutoh13

2009

M. Shapiro, E. Kowalski, B.
Munroe, E. Nanni, J. Sirigiri,
D. Tax, R. Temkin et al.

14

2009

2009

7

8

9

10

11

15

EU-US-JA RF heating technology
workshop 2005

Jun. 15-18, 2005, Santa Cruz,
California, USA

2005-FT3-5

Oct.16-17, 2007, Jeju, Korea

2005-FT3-2
2006-FT3-2

Nov. 27-30, 2007, Himeji, JAPAN

2007-FT3-6
2009-FT3-3

Dec. 9 - 12, 2008, Toki, Japan

2007-FT3-6
2008-FT3-1
2009-FT3-3

Dec. 2-5, 2008, Utsunomiya, Japan

2007-FT3-6
2008-FT3-1
2009-FT3-3

Sept. 15-19, 2008, Pasadena,
California USA

2007-FT3-6
2008-FT3-1
2009-FT3-3

Sept. 10-12, 2008, San Diego,
California, USA

2009-FT3-3

Global Congress on Microwave
Energy Applications GCMEA 2008
MAJIC 1st

Aug. 4-8, 2008, Otsu, JAPAN

2007-FT3-6
2008-FT3-1
2009-FT3-3

Losses, Multimode Propagation and Mode
Conversion in ECH Transmission Lines

US-EU-JPN RF Heating Technology
Workshop 2009

Sept. 16-18, 2009, Fukuoka, Japan

2009-FT3-3

T. Shimozuma, H. Takahashi,
S. Ito, Y. Mizuno et al.

Improvement of Overall Efficiency in Large
Scale ECH System for LHD

26th annual meeting of the Japan
Soc. of Plasma Physics andNuclear Fusion ResearchDec. 1-4, 2009, Kyoto, Japan

2009-FT3-3

T. Shimozuma, S. Kubo, Y.
Yoshimura, H. Igami, H.
Takahashi, R. Ikeda, N.
Tamura, S. Kobayashi, S. Ito,Y. Mizuno, Y. Takita, T.
Mutoh. R. Minami, T. Kariya,
T. Imai, H. Idei, M.A. Shapiro,
R.J. Temkin, F. Felici, T.
Goodman, and O. Sauter

Activities on Realization of High-Power and18th Topical Conference on Radio
Steady-State ECRH System andAchievement of High Performance Plasmas Frequency Power in Plasmas
in LHD

Jun. 24 - 26, 2009, Gent, Belgium

2007-FT3-6
2008-FT3-1
2009-FT3-3

Combline Antenna for Lower Hybrid Current
Korea-Japan workshop on heating
Start-up Experiments in Tokyo Spherical
technology of Fusion plasmas
Tokamak-2

24th annual meeting of the Japan
Soc. of Plasma Physics andNuclear Fusion Research

18th International Toki
Conference (ITC18)

25th annual meeting of the Japan
Soc. of Plasma Physics andNuclear Fusion Research

IRMMW-THz 2008

US-EU-JPN RF Heating Technology
Workshop 2008

A−4

2.4.4Blankets
1䠊JournalPaper
Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

36 (2000) 273-276

2000-FT4-8

283-287 (2000) 52-59

2000
FT4-13
MM-3
MM-25
MM-26

Advances in direct numerical simulation for
Fusion Engineering and Design
MHD modeling of free surface flows

61-62 (2002) 95-102

2000-FT4-7

Evaluation of Flow Structure in Packed-Bed
Fusion Science and Technology
Tube by Visualization Experiment

47 (4) (2005) 1089-1093

2000-FT4-6

Shin-Ya Chiba, Kazuhisa Yuki,
Numerical research on heat transfer
Hidetoshi Hashizume, Saburo
Fusion Engineering and Design
enhancement for high Prandtl-number Fluid
Toda,Akio Sagara

81 (2006) 513-517

2005-FT5-2

2007

Masaaki Satake, Kazuhisa
Yuki, Hidetoshi Hashizume

Reproduction of behavior of 2-D channel
flow with two rods by using k-e model

Fusion Science and Technology

52 (4) (2007) 817-820

2006-FT5-2

2009

H. Hashizume, K. Yuki, N.
Seto, A. Sagara

Feasibility Study of Flibe TBM baaed on
Thermofluid Analysis

Fusion Science and Technology

56 (2) (2009) 892-896

2008-FT5-1

Conference Name

Month Date, Year, Place, CountryYear-Category-No.

Advances in direct numerical simulation for Int. Symp. Fusion Nuclear
MHD modeling of free surface flows
Technology 6

April 7-12, 2002, San Diego, USA

2000-FT4-7

No

Year

Authors

Title of Paper

1

2000

S.Ebara, S.toda and
H.Hahsizume

2

2000

B. van der Schaaf, D.S. Gelles,
Progress and Critical Issues of Reduced
S. Jitsukawa, A. Kimura, R.L.
Activation Ferritic/Martensitic Steel
Klueh, A. Moslang and G.R.
Development
Odette3

2002

S. Satake, T. Kunugi, and S.
Smolentsev

4

2005

Masumi Okumura, Kazuhisa
Yuki, Hidetoshi Hashizume,
Akio Sagara

5

2006

6

7

JournalApplication of Porous Matrix to High Heat
Load Removal

Heat and Mass Transfer

J. Nucl. Mater

2䠊ConferencePaper
No

Year

Authors

Title of Paper

1

2002

S. Satake, T. Kunugi, and S.
Smolentsev

2

2003

Investigation of Non-Isothermal Fluid
K. Yuki, K. Okuyama, S. Toda, Mixing and Wall Temperature Fluctuation in
NURETH-10
H. Hashizume, T. Muramatsu At-Junction which has a 90-degree Bend in
the Upstream Area

October 5-9, 2003, Seoul, Korea

2000-FT4-6

3

2006

S. Toda, K. Yuki, S. Ebara, Y.
Kunikata, J. Abei and H.
Hashizume

August 13-18, Sydney, Australia

2002-FT4-5

Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

8 (2001) 3314-3320

2000-FP5-8

Development of an Advanced Cooling
Device Using Porous Media with Active
Boiling Flow Counter to High Heat Flux

Int. Symp. Fusion Nuclear
Technology 6

2.4.5InVessel/HighHeatFluxMaterialsandComponents
1䠊JournalPaper
No

Year

1

2001

Evidence for the importance of radial
E. M. Hollmann, D.G. Whyte, transport in plasma detachment in theD. Nishijima, N. Ohno et al.
Nagoya University Divertor Simulator(NAGDIS-II)

2

2002

R. E. Nygren

3

2002

K. Tokunaga, R. P. Doerner, R.
Modification of tungsten coated carbon by
Seraydarian, N. Noda, N.
low energy and high flux deuterium
Yoshida, T. Sogabe, T. Kato
irradiation
and B. Schedler

Journal of Nuclear Materials

307-311(2002) 126-129

2000- FT5-10

4

2003

R.P. Doerner, M.J. Baldwin,
S.I. Krasheninnikov, D.G.
Whyte

Behavior of high temperature liquidsurfaces in contact with plasma

Journal of Nuclear Materials

313-316 (2003) 383-387

2002-FT5-1

5

2003

Y. Ueda, K. Tobita, Y. Katoh

PSI issues at plasma facing surfaces ofblankets in fusion reactors

Journal of Nuclear Materials

313-316 (2003) 32-41

2002-FT5-1

2003

J.P. Sharpe, V. Rohde, the
ASDEX-Upgrade experimenta
Charactarization of dust collected fromteam, A. Sagara, H. Suzuki, A.
ASDEX-Upgrade and LHD
Komori, O. Motojima and the
LHD experimental group

Journal of nuclear materials

313-316 (2003) 455-459

2000-FT6-7

6

Authors

Title of Paper

JournalPhysics of Plasmas

Actively cooled plasma facing components
for long pulse high power operation

Fusion Engineering and DesignA−5

60 (2002) 547-564

2002-FT5-1

7

2003

K. Tokunaga, R. P. Doerner, R.
Seraydarian, N. Noda, Y.
Surface morphology and helium retention
Kubota, N. Yoshida, T.
on tungsten exposed to low energy and high Journal of Nuclear Materials
Sogabe, T. Kato and B.
flux helium plasma
Schedler8

2004

D. Nishijima, M.Y. Ye, N.
Ohno, S. Takamura

9

2005

Hisae Togashi, Kazuhisa Yuki, Heat Transfer Enhancement Technique with
Fusion Science and Technology
Hidetoshi Hashizume
Copper Porous Media

10

2005

K. Tokunaga, M.J. Baldwin,
R.P. Doerner, N. Noda, Y.
Kubota, N. Yoshida, T.
Sogabe, T. Kato and B.
Schedler

11

2006

R.E. Nygren, M.A. Ulrickson,
T.J. Tanaka, D.L. Youchison,
ITER first wall Module 19—The US effort
T.J. Lutz, J. Bullock, K.J. Hollis

12

2006

S. TAKAMURA, N. OHNO, D.
NISHIJIMA and S. KAJITA

Formation of Nanostructured Tungsten with
Arborescent Shape due to Helium Plasma
Plasma and Fusion Research
Irradiation

1 (2006) 051

2005-FT5-3

13

2007

N. Ohno, S. Kajita, Dai
Nishijima, S. Takamura

Surface modification at tungsten andtungsten coated graphite due to low energy
Journal of Nuclear Materials
and high fluence plasma and laser pulse
irradiation

363-365 (2007) 1153-1159

2007-FT5-1

14

2009

C.P.C. Wong

Innovative tokamak DEMO first wall anddivertor material concepts

Journal of Nuclear Materials

390-391 (2009) 1026-1028

2007-FT5-1

15

2009

J.P. Sharpe, R.D. Kolasinski,
M. Shimada, P. Calderoni,
R.A. Causey

Retention behavior in tungsten andmolybdenum exposed to high fluences of
deuterium ions in TPE

Journal of Nuclear Materials

390-391 (2009) 709-712

2009-FT5-1

16

2009

M. Miyamoto , D. Nishijima , Observations of suppressed retention and
Y. Ueda , R.P. Doerner , H.
blistering for tungsten exposed to
Kurishita , M.J. Baldwin , et al. deuterium–helium mixture plasmas

49 (2009) 065035

2009-FT5-1

17

2009

R.A. Causey, R. Doerner, H.
Defects in tungsten responsible for
Fraser, R.D. Kolasinski, J.
molecular hydrogen isotope retention after Journal of Nuclear Materials
Smugeresky, K. Umstadter, R.
exposure to low energy plasmas
Williams

390-391 (2009) 717-720

2009-FT5-1

18

2009

S. Sharafat, A. Takahashi, Q.
Hu, N.M. Ghoniem

A description of bubble growth and gas
release of helium implanted tungsten

Journal of Nuclear Materials

386-388 (2009) 900-903

2005-FT5-3

19

2010

H. Kurishita, S. Matsuo, H.
Arakawa, T. Sakamoto, et al.

Development of re-crystallized W–1.1%TiC
with enhanced room-temperature ductility
and radiation performance

Journal of Nuclear Materials

398 (2010) 87-92

2009-FT5-1

Conference Name

Month Date, Year, Place, CountryYear-Category-No.

313-316 (2003) 92-96

2001-FT5-06

Incident ion energy dependence of bubble
formation on tungsten surface with low
energy and high flux helium plasma
irradiation

313-316 (2004) 97

2004-FT5-3

47 (2005) 740-745

2004-FT5-4

337-339 (2005) 887-891

2005-FT5-3
2001-FT5-06

81 (2006) 387-392

2005-FT5-3

Journal of Nuclear Materials

Blister formation and deuterium retention
on tungsten exposed to low energy and high Journal of Nuclear Materials
flux deuterium plasma

Fusion Engineering and Design

Nuclear Fusion

2䠊ConferencePaper
No

Year

Authors

Title of Paper

1

2002

Y. Ueda, K. Tobita, Y. Katoh

PSI issues at plasma facing surfaces ofblankets in fusion reactors

15th International Conference on
Plasma Surface Interactions inControlled Fusion Devices

May 27 - May 31, 2002, Gifu, Japan

2002-FT5-1

2

2003

T. Muroga, H. Watanabe, K.
Fukumoto, M. Satou, A.
Kimura, S.J. Zinkle, N.
Hashimoto, D.T. Hoelzer and
A.L.Qualls

Summary of the Varying Temperature
Irradiation Experiment in HFIR

Proc. of 15th Topical Meeting on
the Technology of Fusion Energy(TOFE-15), Fusion Science andTechnology

Nov.17-21, 2002, Washington,D.C.,
USA

2003
FT5-2
MM-30

3

2004

R. P. Doerner, M. J. Baldwin,
S. I. Krasheninnikov, and K.
SchmidHigh temperature erosion of Beryllium

16th International Conference on
Plasma Surface Interactions inControlled Fusion Devices

May 24-28, 2004, Portland, USA

2002-FT5-1

A−6

4

2007

Kazuhisa Yuki, Akira Matsui,
Hidetoshi Hashizume

Heat removal performance of particlesintered porous media counter to heat flux
input and its phase change characteristics

Second international conferenceon porous media and its
applications in science,engineering and industry

June 17-22,2007,Hawaii, USA

2005-FT5-2

5

2009

H. Kurishita

Markedly Refined W added with TiC
Exhibiting Low DBTT and High Radiation
Durability

14th International Conference on
Fusion Reactor Materials

Sept. 6-11, 2009, Sapporo, Japan

2009-FT5-1

6

2009

R. Nygren

Making Tungsten Work

14th International Conference on
Fusion Reactor Materials

Sept. 6-11, 2009, Sapporo, Japan

2009-FT5-1

JournalVol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

2.4.6Others
1䠊JournalPaper
No

Year

Authors

Title of Paper

1

2003

R. TsujiFlying metal pipe for target transport ininertial fusion energy reactor

Fusion䚷Science䚷and Technol.

43 (2003) 327-333

2002-FT6-5

2

2003

T. Norimatsu, K. Nagai, T.
Takeda, K. Mima, and T.
Yamanaka

Update for the drag force on an injectedpellet and target fabrication for Inertial
fusionFusion Sci. Technol.

43 (2003) 339-345

2002-FT6-5

3

2005

K. Nagai, H. Azechi, F. Ito, A.
Iwamoto, Y. Izawa, T.
Johozaki, R. Kodama, K.
Foam materials for cryogenic targets of fastMima, T. Mito, M. Nakai, N.
Nucl. Fusion
ignition realization experiment (FIREX)
Nemoto, T. Norimatsu, Y.
Ono, K. Shigemori, H. Shiraga,
K. A. Tanaka

45 (2005) 1277-1283

2002-FT6-5

4

2006

K. Furuichi, H. Takata, T.
Motoshima, S. Satake, M.
Nishikawa

Study on behavior of tritium in concrete
wall

Journal of Nuclear Materials

350 (2006) 246-253

2002-FT6-7
2004-FT6-3

5

2006

M. Nishikawa, K. Furuichi, H.
TakataStudy on permeation behavior of gaseous
tritium through concrete walls

Fusion Science and Technology

50 (2006) 521-527

2002-FT6-7
2004-FT6-3

6

2007

K. Furuichi, H. Takata, T.
Motoshima, S. Satake, M.
Nishikawa

Evaluation of tritium behavior in concrete

Journal of Nuclear Materials

360-370 (2007) 1243-1247

2002-FT6-7
2004-FT6-3

7

2008

T. Goto, Y. Ogawa, K. Okano
et al.

Analysis of a core plasma dynamics and dry
Journal of Physics: Conference
wall chamber for fast-ignition IFE power
Seriesplant

112 (2008) 032038 (4pp)

2008-FT6-4

8

2009

T. Goto, Y. Someya, Y. Ogawa Conceptual design of fast-ignition laser
et al.
fusion reactor FALCON-D

49 (2009) 075006 (8pp)

2008-FT6-4

Month Date, Year, Place, CountryYear-Category-No.

Monterey, USA

2002-FT6-5

1-6 Nov. (2004), Vilamoura,
Porutogal, FT/2-1Rb

2002-FT6-5

9-14 September 2007, Kobe, Japan

2007-FT6-4

13-18 October 2008, Geneva,
Switzerland

2007-FT6-4

Nuclear Fusion

2䠊ConferencePaper
No

Year

Authors

Title of Paper

Conference Name

1

2003

T. Norimatsu, K. Nagai, T.
Yamanaka and Y. Izawa

Experimental Simulation on Protection of
Inertial Fusion Science andFinal Optics from Metal Vapor in a Wet-Wall
Application
Laser Fusion Reactor

2

2004

T. Norimastu, H. Azechi, et al.

Development of Key Technologies in DPSSL
System for Fast-ignition, Laser Fusion
Reactor - FIREX, HALNA, and Protection of
Final Optics

3

2007

Analysis of a core plasma dynamics and dry The fifth International Conference
T. Goto, Y. Someya, Y. Ogawa
on Inertial Fusion Sciences andwall chamber for fast-ignition IFE power
et al.
Applications (IFSA2007)
plant

4

2008

T. Goto, Y. Someya, Y. Ogawa Conceptual design of fast-ignition laser
et al.
fusion reactor FALCON-D

20th IAEA Fusion Energy
Conference

22nd IAEA FEC

A−7

CHAPTER3FPPC
Thepublicationlistsinthefourcategoriesof3.4.1SteadystateOperation,3.4.2MHDandHighBeta,3.4.3Confinement,3.4.4Diagnosticsarecombinedintothefollowinglist,becausesomepapersaredifficulttobesortedintoonecategory.
1䠊JournalPaper
Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

Physics of Plasmas

7 (2000) 1863-1869

2000-FP2-14

Y.Oka, Y.Takeiri, K.Tsumori,
M.Osakabe, O.Kaneko,
Performance of LHD-NBI H-ion source
K.Ikeda, M.Hamabe, E.Asano,T.Kawamoto, L.Grisham

Rev.Sci.Instrum.

73 (2002) 1054-1057

2001-FP4-04

2001

M. Ono, M.G. Bell, M. Nagata, Overview of the initial NSTX experimental
et al.
results

Nuclear Fusion

41 (2001) 1435-1447

2000-FP4-8
2000-FP4-9

4

2001

N.Iwasawa, A.Ishida,
L.C.Steinhauer

Physics of Plasmas

8 (2001) 1240-1247

2001-FP2-1

5

2001

Y. Ono, M. Inomoto, Y. Ueda, Fast Compression of Current Sheet during
T. Matsuyama and Y. Murata Externally Driven Magnetic Reconnection

Earth, Planets and Space53 (2001) 521-526

2001-FP2-8

6

2001

L.C.Steinhauer, H.Yamada,
A.Ishida

Physics of Plasmas

8 (2001) 4053-4061

2001-FP2-1

7

2001

Y. Ono, M. Inomoto, T.
Ultra-High-Beta Spherical Tokamak
Matsuyama, T. Murakami and Experiment by Use of Torus Plasma Merging Nuclear Fusion
in TS-3 Spherical Torus Device
T. Tawara

41 (2001) 971-980

2001FP2-8

8

2001

Y. Ono, M. Inomoto, Y. Ueda
and T. Matsuyama

Fast Magnetic Reconnection with
Anomalous Resistivity and Its Application

2 (2001) 473-482

2001-FP2-8

9

2001

Y. Ueda and Y. Ono

High-Power Heating of Spherical Tori by Use
Earth, Planets and Spaceof Merging / Reconnection Phenomena

53 (2001) 527-531

2000-FP2-8
2000-FP2-9

10

2001

Y. Ueda and Y. Ono

Experimental Comparison of Compact RFPs,
Spheromaks, and STs Using Controlled
Nuclear Fusion
Current Drive

41 (2001) 981-984

2000-FP2-9

11

2002

Y.Torii, R.Kumazawa, T.Watari ICRF Heating on LHD using Folded
et al.
Waveguide Antenna

Journal of Plasma Fusion Research

SERIES 5 (2002) 310-313

2000-FP4-6

12

2002

Y.Torii, R.Kumazawa, T.Seki et Plasma Production Experiments using aal.
Folded Waveguide Antenna on LHD

Nuclear Fusion

42, 6 (2002) 679-688

2000-FP4-6

13

2002

A. L. Balandin and Y. Ono

Tomographic Determination of Plasma
Velocity with the Use of Ion Doppler
Spectroscopy

European Physical Journal D

17 (2002) 337-344

2002FP2-1

14

2002

R Sakamoto, H Yamada et al.

Ablation and subsequent Density
Redistribution of Fueling Pellets Injected
into LHD Plasmas

29th EPS Conference on Plasma
Physics and Controlled Fusion

ECA 26B (2002) P1.074

2001-FP2-17

15

2003

P.R. Goncharov, J.F. Lyon, T.
Ozaki, S. Sudo and LHD
Experimental GroupA Numerical Approach to the Localization of
Journal of Plasma and Fusion
Passive Line Integrated Neutral Particle
Research Series
Measurements on LHD

6 (2003)

2003-FP5-15

16

2003

P.R. Goncharov, T. Saida, N.
Tamura, T. Ozaki, M. Sasao,
Development and Initial Operation of the
M. Isobe, S. Sudo, K.V.
Pellet Charge Exchange Diagnostic on LHD
Khlopenkov, A.V. Krasilnikov,
Heliotron
V.Yu. Sergeev, and LHD
Experimental Groups

Review of Scientific Instruments

74 (2003) 1869-1872

2003-FP5-15

17

2003

Tetsuo Ozaki, Sadayoshi
Murakami, et al.

Review of Scientific Instruments

74-3 (2003) 1878-1882

2003-FP5-15

18

2003

D. Mueller, M. Ono, M.G. Bell,
Results of NSTX Heating Experiments…, M. Nagata,…,et al.

31 (2003) 60-67

2001-FP4-07
2001-FP4-8
2002-FP4-6
2002-FP5-37

No

Year

Authors

1

2000

Y. Ono and M. Inomoto

2

2001

3

Title of Paper

JournalUltra-High Beta Spherical Tokamak
Formation by Use of Oblate Field-Reversed
Configuration

Linear Gyroviscous Stability of FieldReversed Configurations with Static
Equilibrium

Two-Fluid Flowing Equibliria of Compact
PlasmasSpatial resolved high energy particle
diagnostic system using time-of-flightneutral particle energy analyzer in Large
Helical Device

Science and Technology ofAdvanced MaterialIEEE Trans. Plasma Science

A−8

2003

M.Gilmore, W.A.Peebles.,S.Kubota, X.V.Nguyen, andA.Ejiri

Progress toward a practical magnetic field
diagnostic for low-field fusion plasmas
based on dual mode correlationreflectometry

Rev. Sci. Instrum.

74 (2003) 1469-1472

2002-FP5-37

20

2003

Y.Oka, K.Tsumori, Y.Takeiri,
K.Ikeda, O.Kaneko,
K.Nagaoka, M.Osakabe,
E.Asano, T.Kawamoto,
T.Kondo, M.Sato, L.Grisham,
A.Honda, N.Umeda,
T.Yamamoto

Studied of H- source for large helical deviceRev.Sci.Instrum.
neutral beam injector(invited)

75 (2004) 1803-1808

2003-FP4-1

21

2003

J.R. Wilson, et al.

Exploration of high harmonic fast wave
heating on the National Spherical Tokamak
Experiment

10 (2003) 1733-1738

2001-FP4-8
2002-FP4-6

22

2003

A. L. Balandin, Y. Ono and Y.
MurataRadial Velocity Profile Reconstruction by Ion
European Physical Journal D
Doppler Spectroscopy Measurements

27 (2003) 125-130

2003FP2-8

23

2003

E.J. Synakowski, M.G. Bell,…,M. Nagata,…, et al.

The national spherical torus experiment(NSTX) research programme and progress
towards high beta, long pulse operating
scenarios

43 (2003) 1653-1664

2001-FP4-8
2001-FP4-7
2002-FP4-6

24

2003

M. Ono, M.G. Bell,…,M.
Nagata,…, et al.

Progress towards high-performance, steadyPlasma Phys. Control. Fusion
state spherical torus

45 (2003) A335-A350

2001-FP4-7
2001-FP4-8
2002-FP4-6

25

2003

Y. Ono, T. Kimura, E.
Kawamori, Y. Murata, S.
Miyazaki, Y. Ueda, M.
Inomoto, A. L. Balandin and
M. KatsuraiFirst and Second-Stable Spherical Tokamaks
Nuclear Fusion
in Reconnection Heating Experiments

43 (2003) 789-794

2003FP4-4

26

2003

Y. Ono, T. Kimura, T. Murata,
High-Beta Characteristics of First and
S. Miyazaki, Y. Ueda, M.
Second-Stable Spherical Tokamaks in
Inomoto, K. Arimoto, A. L.
Reconnection Heating Experiments of TS-3
BalandinFusion Energy 2002

(2003) EX/P3-15

2002FP4-5

27

2003

Y. Ono, T. Matsuyama, K.
Umeda and E. Kawamori

Spontaneous and Artificial Generation of
Sheared Flow in Oblate FRCs

Nuclear Fusion

43 (2003) 649-654

2003FP2-8

28

2003

M. Isobe, D.S. Darrow, J.
Kotani, A. Shimizu, C. Suzuki,
Y. Yoshimura, T. Minami, C.
Takahashi, K. Nagaoka, S.
Nishimura, K. Toi, K.
Matsuoka, S. Okamura, andthe CHS group

Energy and pitch angle-resolved
measurements of escaping helically trapped
Review of Scientific Instruments
energetic ions at small major radius side ofCHS

74 (2003) 1739-1742

2003-FP-2-4

29

2003

H. Gota, K. Fujimoto, Y.
Separatrix shapes and internal structures ofPhys. Plasmas
Ohkuma, T. Takahashi, and Y.
a field-reversed configuration plasma
Nogi

10 (2003) 4763-4770

2004-FP5-37

30

2003

H. Gota, T. Akiyama, K.
Fujimoto, Y. Ohkuma, Ts.
Takahashi, and Y. Nogi

Separatrix shape measurement on fieldreversed configuration plasmas

Rev. Sci. Instrum.

74 (2003) 2318-2323

2004-FP5-37

31

2004

P.R. Goncharov, T. Ozaki, S.
Sudo, N. Tamura, et al.

Digital Processing of Solid State Detector
Signals in Pellet Charge Exchange
Measurements on LHD

Review of Scientific Instruments

75 (2004) 3613-3615

2003-FP5-15

32

2004

T.Ozaki, P.Goncharov,
S.Murakami, S.Sudo,
H.Sanuki, et al.

Two-dimensional scanning high-energy
particle diagnostic system in Large Helical
Device

Review of Scientific Instruments

75-10 (2004) 3604-3606

2003-FP5-15

33

2004

Search and retrieval method of similar
plasma waveforms

Fusion Engineering and Design

71 (2004) 189-193

2004-FP5-39

34

2004

M. Ignatenko, A. Mase, L.
Bruskin et al.

Microwave Imaging Reflectometry of
Corrugated Metal Targets

J. Plasma Fusion Res

80, 2 (2004) 87-89

2004-FP5-18

35

2004

M. Ignatenko, A. Mase, L. G.
Bruskin et al.

Effects of Asymmetry and Target Location
on Microwave Imaging Reflectometry

Rev. Sci. Instrum

75, 10 (2004) 3810-3812

2004-FP5-18

36

2004

Y. Kogi, K. Uchida, A. Mase et
Ultrashort-Pulse Reflectometer on LHD
al.

Rev. Sci. Instrum

75, 10 (2004) 3837-3839

2004-FP5-18

19

H. Nakanishi, T. Hochin, M.
Kojima, LABCOM group

Phys. Plasmas

Nucl. Fusion

A−9

37

2004

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Initial angle resolved measurements of fastneutrals using a multichannel linear AXUV
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H. Nakanishi, T. Hochin, M.
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Measurement of global instability of
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Development of the two-dimensionalThomson scattering diagnostic system by
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M. Isobe, K. Toi, H.
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Research and Development on
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Development of Excited Helium BeamT. Nishi, K. Yoneda, K. Masuda
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Yamashita, T. Hayamizu and centre solenoid in TS-4
Y. Ono,Nuclear Fusion

123

2007

M. Nagata, R. Raman, V.
Soukhanowskii, B.A. Nelson,
T.R. Jarboe, D.Mueller andthe NSTXExB Plasma rotation and n=1 oscillation
observed in the NSTX-CHI experiments

124

2007

S.Masamune et al.

Research Plans for Low-Aspect Ratio
Reversed Field Pinch

125

2007

Inductive Sustainment of a Field-Reversed
S.P. Gerhardt, E..V. Belova, M.
Configuration Stabilized by Shaping,
Yamada, H. Ji, M. Inomoto, Y.
Magnetic Diffusion, and Finite-LarmorRen, B. McGeehan
Radius Effects

126

2007

127

128

Spectroscopic observations of beam andsource plasma light and testing Csdeposition monitor in the large area
negative ion source for LHD-NBI

79 (2008) 02C105-1-5

2007-FP2-2

47 (2007) S645-S657

2005-FP2-6

2 (2007) 424-430

2007FP4-1

47 (2007) 1232-1237

2007FP4-1

Plasma and Fusion Research:
Rapid Communications

2 (2007) 0035

2004-FP4-3

Trans. Fusion Sci. Technol.

51 (2007) 197-199

2006-FP2-7

Phys. Rev. Lett.

99 (2007) 245003

2005-FP4-5

T. Sumikawa, K. Yamashita, E. Development of 2-D Thomson Scattering
Kawamori, K. Narihara and Y. Measurement Using Multiple Reflection and Plasma and Fusion ResearchOno
the Time-of-Flight of Laser Light

2 (2007) S1108-1-4

2007FP4-1

2007

Y. Ono, R. Imazawa, H.
Imanaka, T. Hayamizu, M.
Inomoto, M. Sato, E.
Kawamori, A. Ejiri, Y. Takase,
T. Asai, T. Takahashi

Fusion Energy 2006

(2007) EX/P7-12

2007FP3-2

2007

M. Isobe, S. Okamura, K.
Nagaoka, M. Osakabe, K. Toi,
Fast-ion-diagnostics for CHS experiment
Y. Yoshimura, K. Matsuoka,
M. Sasao, D.S. Darrow

Plasma Fusion Research

2 (2007) S1076

2003-FP-2-4

2007

Toshiki TAKAHASHI, Hidefumi
YAMAURA, Fusaki P. IIZIMA,
Yoshiomi KONDOH, Tomohiko
ASAI, Tsutomu TAKAHASHI,
A New Explanation for Toroidal Spin-Up of a
Plasma and Fusion Research
Yoshiki MATSUZAWA, Taichi Field-Reversed Configuration
OKANO, Yoichi HIRANO,
Naoki MIZUGUCHI, Yukihiro
TOMITA and Shigeru INAGAKI2008 (2007) 1-2

2007-FP3-1

130

2007

T. Asai, Y. Matsuzawa, T.
Okano, T. Kiguchi, K.
Sakuraba, Ts. Takahashi, To.
Takahashi, Y. Hirano, N.
Mizuguchi, and Y. Tomita

Heating and Particle Build-Up of FieldReversed Configuration due to Neutral
Particle Injection in a Translation Process

Transaction of Fusion Science andTechnology

51 (2T) (2007) 379-381

2007-FP3-1

131

2007

Hidefumi Yamaura, Toshiki
Takahashi, Yoshiomi Kondoh, Rotation of a Field-Reversed Configuration
Tomohiko Asai, Tsutomu
due to Resistive Flux Decay Confinement
TakahashiTransaction of Fusion Science andTechnology

51 (2T) (2007) 373-375

2006-FP2-3

2008

Tetsuo Ozaki, Pavel R.
Goncharov, Evgeny A.
Veshchev, Shigeru Sudo,
Tetsuo SEKI, Hirofumi
KASAHARA, Yuichi TAKASE,
Takuya OHSAKO

3 (2008) S1084/1-4

2004-FP5-19

129

132

Rev.Sci.Instrum.

Transient and Intermittent Magnetic
Reconnection in TS-3 / UTST Merging
Startup Experiments

Helium ion observation during 3rd harmonic
Plasma and Fusion Research
ion cyclotron heating in Large Helical Device

A−15

133

2008

T.Ozaki, P.Goncharov,
E.Veshchev, N.Tamura,
S.Sudo, T. Seki, H. Kasahara,
Y. Takase, and T. Ohsako

Pellet Charge Exchange Helium
measurement Using Neutral Particle
Analyzer in Large Helical Device

134

2008

P. Goncharov, T. Ozaki, I.
Tolstikhina et al.

135

2008

136

79 (2008) 10E518/1-4

2004-FP5-19

Calculation of Light Impurity Pellet Induced
Fluxes of Charge Exchange Neutral Particles
Review of Scientific Instruments
Escaping from Magnetically Confined
Toroidal Plasmas

79 (2008) 10E312

2004-FP5-19

P. Goncharov, T. Ozaki, E.
Veshchev et al

Analysis of Anisotropic Suprathermal Ion
Distributions Using Multidirectional
Measurements of Escaping Neutral Atom
Fluxes

Review of Scientific Instruments

79 (2008) 10F311

2004-FP5-19

2008

Goncharov P.R., Ozaki T.,
Veshchev E.A. and Sudo S

Ion Distribution Function Evaluation Using
Escaping Neutral Atom Kinetic Energy
Samples

Plasma and Fusion Research

3 (2008) S1083

2004-FP5-19

137

2008

E. Veshchev, T. Ozaki, P.
Goncharov, et al.

Analysis of the Impurities Influence on the
Attenuation of Fast Particles and the Shape
Review of Scientific Instrumentsof the Measured Fast Ion Spectra in the
Large Helical Device (LHD)

79 (2008) 10E310

2004-FP5-19

138

2008

Simulation of Angle and Energy Resolved
E. Veshchev, P. Goncharov, T. Fluxes of Escaping Neutral Particles from
Fusion Plasmas with Anisotropic Ion
Ozaki et al
Distributions

Plasma and Fusion Research Series

3 (2008) S1035

2004-FP5-19

139

2008

N. NISHINO, S. PAUL, R. KAITA Status of Two-Dimensional Ion Velocity
and A.L. ROQUEMORE
Measurement System in NSTX

JPFRS

8 (2008) 640-644

2008-FP5-4
2007-FP5-7

140

2008

T. Hochin, K. Koyama, H.
Nakanishi, M. Kojima,
LABCOM group

Fusion Engineering and Design

83 (2008) 417-420

2004-FP5-39

141

2008

T. Liang, X. Kong, Z. Shen,
C.W. Domier and N.C.
New Advances of the ECE Plasma
Luhmann, Jr., Hyeon K. Park, Visualization System for KSTAR Tokomak
N. Ito, A. Mase, and E. Sakata

Proc. Joint Workshop on ECE and
ECRH, Yosemite

2008

2007-FP5-6

142

2008

Lu. Yang, N. Ito, C. W. Domier, 18- to 40 GHz Beam Shaping/Steering
N. C. Luhmann, Jr. and A.
Phased Antenna Array System using Fermi
Mase
AntennaIEEE Trans. Microw. Theory Tech.

56, 4 (2008) 767-773

2007-FP5-6

143

2008

Measurement of Edge Density Profiles of
Y. Yokota, A. Mase, Y. Kogi etLarge Helical Device Plasmas Using anal.
Ultrashort-Pulse Reflectometer

Rev. Sci. Instrum

79, 5 (2008) 056106/1-3

2007-FP5-6

144

2008

N. Ito, A. Mase, Y. Kogi et al.

New Advanced Fabrication Technique for
Millimeter-Wave Planar Components based
Jpn. J. Appl. Phys
on Fluororesin Substrates using Graft
Polymerization

47, 6 (2008) 4755-4758

2007-FP5-6

145

2008

Y. Yokota, A. Mase, Y. Kogi et Reconstruction of Edge Density Profiles onal.
LHD Using Ultrashort-Pulse Reflectometry

Rev. Sci. Instrum

79, 10 (2008) 10F112/1-3

2007-FP5-6

146

2008

Y. Yokota, A. Mase, Y. Kogi et Ultra-Wide Band Radar Reflectometer foral.
Measurement of Plasma Density Profiles

Proc. 11th IEEE Int. Conf, on
Communication Technology(2008) 313-315

2007-FP5-6

2008

Q.R. Marksteiner, T.S.
Pedersen, J.W. Berkery, M.S.
Hahm, J.M. Mendez, B.
Durand De Gevigney, and H.
HimuraPhys. Rev. Lett.

100 (2008) 065002-1 – 065002-4

2005-FP5-17

147

Review of Scientific Instruments

Extension of frequency-based dissimilarity
for retrieving similar plasma waveforms

Observations of an ion-driven instability in
non-neutral plasmas confined on magnetic
surfaces

A−16

148

2008

S. P. Gerhardt, E. V. Belova,
M. Yamada, H. Ji, Y. Ren, B.
McGeehan, M. Inomoto

Field-reversed configuration formation
scheme utilizing a spheromak and solenoid
induction

Phys. Plasmas

15 (2008) 032503

2005-FP4-5

149

2008

S.P. Gerhardt, E.V. Belova, M.
Yamada, H. Ji, M. Inomoto,
C.M. Jacobson, R. Maqueda,
B. McGeehan, Y. Ren

Inductive sustainment of oblate fieldreversed configurations with the assistancePhys. Plasmas
of magnetic diffusion, shaping, and finiteLarmor radius stabilization

15 (2008) 022503

2005-FP4-5

150

2008

S.P. Gerhardt, E.V. Belova, M. New method for inductively forming an
Yamada, H. Ji, M. Inomoto, Y. oblate field reversed configuration from aRen, B. McGeehan
spheromak

48 (2008) 032001

2005-FP4-5

151

2008

T. Kanki, L. C. Steinhauer, M.
NagataPlasma and Fusion Research

3 (2008) S1066-1 - S1066-7

2006-FP2-7

2008

T.S. Pedersen, J.W. Berkery,
A.H. Boozer, P.W. Brenner, B.
Dynamics of electron-rich plasmas in the
Durand de Gevigney, M.S.
CNT stellarator
Hahm, Q.R. Marksteiner, and
H. Himura

Plasma and Fusion Research

3 (2008) S1022-1 – S1022-6

2005-FP5-17

153

2008

Y. Ono, R. Imazawa, H.
Imanaka, Y. Hayashi, S. Ito, M.
Nakagawa, T. Yamada, M.
Ion and Electron Heating Characteristics ofInomoto, A. Ejiri, Y. Takase, T. Magnetic Reconnection in TS-3 and UTST
Asai, T. Takahashi, H.
Merging Startup Experiments
Sakakita, S. Kiyama, Y. Hirano,
H. Koguchi, C. Z. Cheng

Fusion Energy 2008

(2008) EX/P9-4

2008FP3-1

154

2008

Effects of background neutral particles on aY. Matsuzawa, T. Asai, Ts.
field-reversed configuration plasma in the
Takahashi, and To. Takahashi
translation process

Phys. Plasmas

15 (2008) 082504, 1-8

2007-FP3-1

155

2009

Tetsuo Ozaki, Pavel R.
Goncharov, Evgeny A.
Veshchev Naoki Tamura,
Tetsuo SEKI

8 (2009) 1089-1094

2004-FP5-19

156

2009

K. Masuda, T. Nakagawa, T.
Built-In Ion Source for Inertial Electrostatic
Kajiwara, H. Zen, K. Yoshikawa
Confinement in Low Pressure Regime
and K. Nagasaki

Fusion Science and Technology

56 (2009) 523-527

2009-FP5-1

157

2009

K. Masuda, T. Fujimoto, T.
Nakagawa, H. Zen, T.
Kajiwara, K. Nagasaki and K.
Yoshikawa

Diagnostic System Development for D-D and
D-3He Reaction Distributions in an Inertial
Fusion Science and Technology
Electrostatic Confinement Device byCollimated Proton Measurements

56 (2009) 528-532

2009-FP5-1

2009

K. Yoshikawa, K. Masuda, T.
Takamatsu, Y. Yamamoto, H.
Results of the Development of theToku, T. Fujimoto, E. Hotta, K.
Humanitarian Landmine Detection System
Yamauchi, M. Ohnishi, H.
by a Compact Fusion Neutron Source andOsawa, S. Shiroya, T. Misawa,
Dual Sensors
Y. Takahashi, Y. Kubo and T.
Doi

AIP Conference Proceedings

1099 (2009) 652-655

2009-FP5-1

159

2009

K. Masuda, T. Takamatsu, K.
Yoshikawa, T. Misawa, S.
Shiroya, Y. Takahashi, T.
Fujimoto, T. Nakagawa, T.
Kajiwara and K. Nagasaki

Research and Development of Compact
Neutron Sources based on Inertial
Electrostatic Confinement Fusion

AIP Conference Proceedings

1099 (2009) 652-655

2008-FP5-8

160

2009

K.Tomiyasu, K.Yokoyama,
K.Yamauchi, M.Watanabe,
A.Okino, and E.Hotta

Effects of Cusp Magnetic Field in a
Cylindrical Radially Convergent Beam Fusion Fusion Science and Technology
Device56 (2009) 967-971

2008-FP5-8

161

2009

Y. Yamamoto, A. Ishidou, K.
Noborio, S. Konishi

Neutron Beam Generation by the Cylindrical
Fusion Science and Technology
Fusion Neutron Source

56 (2009) 761-765

2008-FP5-8

152

158

Two-Fluid Flowing Equilibria of Helicity
Injected Spherical Torus with Non-Uniform
DensityNucl, Fusion

Radial Profiles of High-Energy Particles in
Journal of Plasma and Fusion
NBI and ICH Plasmas Measured by Pellet
Charge Exchange Technique on Large Helical Research Series
Device

A−17

162

2009

A. Mase, Y. Kogi, N. Ito et al.

Advanvement of Microwave Diagnostics for
Plasma Devices and Operations
Magnetically Confined Plasmas

17, 2 (2009) 98-116

2007-FP5-6

163

2009

K. Akaki, A. Mase, Y. Kogi etal.

Study of Dual-Dipole Antenna Array for
Millimeter Wave Imaging(2009) R5E41-0055

2009-FP5-2

164

2009

Equilibrium reconstruction and estimation
A. Sanpei, K. Oki, R. Ikezoe, etof neoclassical effect in low-aspect-ratio RFP J. Phys. Soc. Jpnal.
experiments on RELAX

78, No.1(2009) 013501

2006-FP2-8

165

2009

A. Sanpei, K. Oki, R. Ikezoe, et Characterization of equilibria in a lowal.
aspect-ratio RFP

8 (2009) 1066

2006-FP2-8

166

2009

R. Raman, T.R. Jarboe,
M.Nagata, et al.

49 (2009) 65006-65011

2006-FP4-3
2007-FP3-5

167

2009

T. Asai, Y. Matsuzawa, N.
Yamamoto, K. Takao, H.
Translation of Field-Reversed Configuration
Tamura, M. Hiyoshi, T. Sasaki,
Journal of Plasma and Fusion
into a Confinement Region Filled with
Ts. Takahashi, Y. Nogi, M.
Research SERIES (JPFR SERIES)
Neutral Gas
Inomoto, To. Takahashi, J.
Miyazawa, Y. Narushima

8 (2009) 1058-1061

2009-FP3-3

168

2009

Y. Matsuzawa, T. Asai, Ts.
Takahashi, To. Takahashi, etal.

Particle and Energy Recovery Process of aHigh-Beta Compact Toroid Translated Along Fusion Science and Technology
an Asymmetric Mirror Field

55(2T) (2009) 76-81

2008-FP4-1

169

2009

N. Yamamoto, Y. Matsuzawa,
Self-Generated Toroidal Flow in a High-Beta
T. Asai, Ts. Takahashi, To.
Fusion Science and Technology
Compact Toroid with Mirror Configuration
Takahashi, et al.

55(2T) (2009) 87-90

2008-FP4-1

170

2010

H. Nakanishi, et al.

5 (2010) S1042

2008-FP5-7

Month Date, Year, Place, CountryYear-Category-No.

43rd Annual Meeting of theDivision of Plasma Physics, APS

Nov. 2000, Quebec Canada

2000-FP2-14

University of Tokyo Symposium2000 on Magnetic Reconnectionin Space and Laboratory Plasmas,

Feb.-Mar., 2000, Tokyo, Japan

2000-FP2-8

Nov. 2000, Quebec, Canada

2000-FP2-9

Dec.9-12, 2000, Toki, Japan

2000-FP4-6

2001, Oxnard, California

2000-FP4-8

Dec.11-14, 2001, Toki, Japan

2000-FP4-6

2001, Oxnard, California

2000-FP4-8

May, 2001, Princeton, USA

2001-FP2-8

Proc. 34th Int. Conf. on Infrared,
Millimeter, and Terahertz Wave

J. Plasma Fusion Res. SERIESSolenoid-free plasma start-up in NSTX using
Nucler Fusiontransient CHI

Clustered Data Storage for Multi-site Fusion
Plasma and Fusion ResearchExperiments

2䠊ConferencePaper
No

Year

Authors

Title of Paper

Conference Name

1

2000

A. L. Balandin, Y. Ono

2

2000

Y. Ono, T. Murakami, M.
Fast Reconnection Mechanisms in TS-3
Inomoto, Y. Ueda, T.
Merging Experiment
Matsuyama, and H. Hayashiya

3

2000

Y. Ono, Y. Ueda, T.
Matsuyama, M. Tsuruda, M.
Inomoto, H. Hayashiya,
M.Katsurai

4

2000

13th International Toki
Y.Torii, R.Kumazawa, T.Watari Ray tracing calculation of shear Alfven wave
Conference on Plasma Physics andet al.
on LHD
Contrlooed Nuclear Fusion

5

2001

B.P. LeBlanc, et al.

3-D tomography diagnostic system forspherical tokamaks

Formation of Compact RFP, Spheromak and43rd Annual Meeting of the
ST in TS-3 Device and Their Merging
Division of Plasma Physics, APS
Magnetic Reconnection

High-Harmonic Fast-Wave Heating in NSTX

14th Top. Conf. on Radio
Frequency Power in Plasmas

Joint Conference of 12th
InternationaToki Conference on
Plasma Physics and Contrlooed
Nuclear Fusion and 3rd General
Scientific Assembly of Asia Plasma
and Fusion Associationl

6

2001

Y.Torii, R.Kumazawa, T.Watari Ion Berstein wave heating using folded
et al.
waveguide antenna on LHD

7

2001

J.R. Wilson, et al.

Plasma Response to the Application of 30
MHz RF Power in the NSTX Device

8

2001

Y. OnoUS-Japan Workshop on Physics ofRecent Progress of Laboratory Reconnection
Plasma Merging and Magnetic
Experiment at TS-3/ 4
Reconnection

14th Top. Conf. on Radio
Frequency Power in Plasmas

A−18

9

2001

Y. OnoIPELS(Interrelation between
Recent Progress of Laboratory Reconnection
Plasma Experiments in Laboratory
Experiments at TS-3 and 4
and Space) '01

10

2001

J.C. Hosea, et al.

Results of High Harmonic Fast Wave Heating 28th EPS Conf. on Controlled
Experiments on NSTX
Fusion and Plasma Physics

11

2001

Y. Ono, Y. Ueda, T.
Matsuyama, T. Murata, M.
Inomoto and M. Katsurai

Ultra-High-Beta Spherical Tokamak
Experiments in TS-3 and 4

12

2002

R. Raman, M. Bell,…,M.
Nagata,…, et al.

13

2002

Y. OnoCurrent Sheet Structures in TS-3 and 4
Reconnection Experiments

14

2002

The 14th Topical Conference on
A. Mase, Y. Kogi, M. Ohashi etElectron Cyclotron Emission Imaging on LHD High- Temperature Plasmaal.
Diagnostics

Jul. 8-11, 2002, Madison, USA

15

2002

Y. Ono, E. Kawamori, T.
Matsuyama, M. Tsuruda, T.
Kimura, K. Sato, T. Okazakio

34th Science Assembly of theCommittee on Space Research(COSPER)

Oct. 2002, Houston, TX, USA

16

2002

A. Mase, Y. Kogi, K. Kawahata Progress in Millimeter-Wave Imaging
et al.
Diagnostics

The 4th International Conference
on Open Magnetic Systems for
Plasma Confinement

Jul. 1-4, 2002, Jeju, Korea

17

2002

T.R. Jarboe, R. Raman,…,M.
Nagata,…, et al.

Progress with Helicity Injection Current
Drive

The 19th IAEA Fusion Energy
Conference

18

2002

Y. Ono

19

2002

20

Jul. 2001, Niseko, Japan

2001-FP2-8

June 18-22, 2001, Funchal, Portugal

2000-FP4-8

Aug, 2001䠈Sao Jose dos Campos䠈
Brazil

2001-FP4-6

29th European Physical Society
Coaxial Helicity Injection for plasma start-up
Meeting on Controlled Fusion andin NSTX
Plasma Physics

June 17-21, 2002, Montreux,
Switzerland

2001-FP4-07

US-Japan Symposium on Plasma
Merging and Magnetic
Reconnection (MR2002)

Nov. 2002, Hakone, Japan

2002-FP2-1

Joint Meeting of the 2nd
International Atomic Energy
Agency Technical Committee
Meeting on Spherical Tori and 7thInternational Spherical Torus
Workshop

Helicity Evolutions of Merging spheromaks
with Co- and Counter-Helicity in TS-3 and 4
Experiments

2002-FP2-1

Oct. 14-19, 2002, Lyon, France

2001-FP4-07

Reconnection Startup/ Heating of High-Beta
45th Annual Meeting of theSpherical Tokamaks (STs) in TS-3/ 4
Division of Plasma Physics, APS
Experiments

Nov. 2002, Orlando, FL, USA

2002-FP4-5

E.J. Synakowski, M.G. Bell,…,M. Nagata,…, et al.

The National Spherical Torus Experiment(NSTX) Research Program and Progress
Towards High Beta, Long Pulse Operating
Scenarios

The 19th IAEA Fusion Energy
Conference

Oct. 14-19, 2002, Lyon, France

2001-FP4-07

2003

Y. Ono and TS-3/4 group

Current Sheet / Plasmoid Ejections andPlasma Heating in TS-3 and 4 Reconnection
Experiments

MR2003 Symposium / Fifth USJapan Symposium on Magnetic
Reconnection, Plasma Merging
and Magnetic Jet

Nov. 2003, Los Angeles, CA, U.S.A.

2003-FP2-8

21

2003

M. Isobe, H. Matsushita, D.S.
Darrow, Y. Yoshimura, T.
Minami, A. Shimizu, K.
Experimental study on losses of energetic
Nagaoka, M. Nishiura,
ions by use of diagnostic neutral beam in
C. Suzuki, S. Nishimura, T.
CHS
Akiyama, K. Ida, K. Toi, K.
Matsuoka and S. Okamura

8th IAEA Technical Meeting on
Energetic Particles in Magnetic
Confinement Systems

Oct. 6-8, 2003, San Diego, USA

2003-FP-2-4

22

2003

Y. OnoFormation and stability of compact RFP in
TS-3 and 4 experiment

The 9th-IEA/RFP-Workshop

Mar. 2003, Tsukubas, Japan

2002-FP4-5

23

2003

A. Ishida, C.O. Harahap, L.C.
Steinhauer, Y.-K. M. Peng

Improved formalism for flowing two-fluid
equilibrium and its application to ST

The 13th Toki Conference

December 9-12, 2003, Toki, Japan

2003-FP2-12

24

2003

Y. OnoIon Heating Characteristics of Magnetic
Reconnection in TS-3 and 4 Merging
Experiments

Seventh International Workshop
on the Interrelationship between
Plasma Experiments in the
Laboratory and in Space

July, 2003, Whitefish, MN, U.S.A.

2003-FP2-8

A−19

General Meeting of Center for
Magnetic Self-Organization inLaboratory and Astrophysical
Plasmas,Nov., 2003, Chicago, IL, U.S.A

2003-FP2-8

APS Division of Plasma Physics
Meeting 2003

Oct. 27-31, 2003, Albuquerque, USA

2002-FP5-37

Collisional ripple transport of neutral beam46th Annual Meeting of theinjected energetic ions in low aspect ratio
Division of Plasma Physics
helical system CHS

November 15-19, 2004 Savannah,
GA, USA

2003-FP-2-4

M. Ignatenko, A. Mase, L.
Bruskin et al.

The 16th Topical Conference on
Effects of asymmetry and target location on
High-Temperature Plasma
microwave imaging reflectometry
Diagnostics

Apr. 19-22, 2004, San Diego, USA

2004-FP5-18

M. Ignatenko, A. Mase, L.
Bruskin, Y. Kogi, H. Hojo

Numerical Study of Microwave Imaging
Reflectometer for a Tandem Mirror Device

The 5th International Conference
on Open Magnetic Systems for
Plasma Confinement

Jul. 7-9, 2004, Novosibirsk, Russia

2004-FP5-18

International workshop on
Transient and Intermittent Magnetic"Explosive Phenomena in
Reconnections in TS-3/ 4 Tokamak Merging Magnetized Plasma - New
Experiments
Development of Reconnection
Research

Mar. 2004, Kyoto, Kyoto, Japan

2004-FP2-1

25

2003

Y. OnoJapanese Reconnection COE Project

26

2003

S. Kubota, W.A. Peebles, X.V.
Nguyen, A. Ejiri, R. Kaita, A.L. Millimeter-Wave Measurements on NSTX
Roquemore, G. Taylor

27

2004

M. Isobe, H. Matsushita, Y.
Yoshimura, K. Nagaoka, T.
Minami, T. Akiyama, C.
Suzuki, S. Nishimura,
M. Nishiura, K. Toi, K.
Matsuoka, S. Okamura, D.A.
Spong and D.S. Darrow

28

2004

29

2004

30

2004

Y. Ono and TS-3/4 group

31

2004

Y. Kogi, K. Uchida, A. Mase et
Ultrashort-pulse reflectometer on LHD
al.

The 15th Topical Conference on
High-Temperature Plasma
Diagnostics

Apr. 19-22, 2004, San Diego, USA

2004-FP5-18

32

2005

Y. Kogi, A. Mase, K. Kudo etal.

The 30th International Conferenceon Infrared and Millimeter Waves

Sept. 19-23, 2005, Williamsburg,USA

2004-FP5-18

33

2005

American Physics Society, 47th
S.P. Gerhardt, M. Yamada, H. Equilibrium Reconstruction Techniques
Annual Meeting of the Division ofJi, M. Inomoto
Applied to Compact Toroid Plasmas in MRX
Plasma Physics

Oct. 24–28, Denver, USA

2005-FP4-5

34

2005

Y. Ren, M. Yamada, S.P.
Gerhardt, H. Ji, R. Kulsrud, A.
Kuritsyn, M. Inomoto

Experimental Studies of the Hall Effect andFluctuations in MRX

Oct. 24–28, Denver, USA

2005-FP4-5

35

2005

Y. Ono and TS-3/4 Group

Heating Properties of Merging Startup in TS- 48th Annual Meeting of the
3/4/5 High-Beta ST Experiments
Division of Plasma Physics, APS

2005 Denver, Co, USA

2004-FP4-5

36

2005

Y. OnoJoint Meeting of the 3rd IAEA
Heating Properties of Merging/Technical Meeting of Spherical
Reconnection Startup in TS-3/4 High-Beta ST
Tori and the 11th International
Experiments
Workshop on Spherical Torus

Oct. 2005 St. Petersburg, Russia

2005-FP2-4

37

2005

T.Ozaki, P.Goncharov,
S.Murakami, E.Veschev,
S.Sudo, et al.

Horizontal and Vertical Structure of theHigh-Energy Particle Distribution in large
Helical Device

Proceedings of a Technical
Meeting Takayama

Nov. 9-11, 2005, IAEA-TM-27024

2003-FP5-15

38

2005

A. Mase, L. Bruskin, Y. Kogi et Microwave Imaging and Reflectometry foral.
LHD Plasma

US-Japan Workshop on Study ofAdvanced Fluctuation Diagnostic
MethodMar. 21-23, 2005, Princeton, USA

2004-FP5-18

39

2005

M. Ignatenko, A. Mase, L.
Bruskin et al.

Sept. 26-29, 2005, Snowbird, USA

2004-FP5-18

40

2005

M. Inomoto, S. P. Gerhardt, Y. Reconnection and Ion Acceleration
Yamada, H. Ji, B. McGeehan, Processes during Counter Helicity Merging
A. Kuritsyn, Y. Ren, E. Belova of Spheromaks in the MRX

Oct. 24–28, Denver, USA

2005-FP4-5

Development of New Detector forMillimeter-Wave Imaging

American Physics Society, 47th
Annual Meeting of the Division of
Plasma Physics

Numerical Study of Microwave Imaging
Reflectometry for Measurements of Density The 12th International Symposium
Fluctuations Spectra for GAMMA10
on Laser-Aided Plasma Diagnostics
Geometry

American Physics Society, 47th
Annual Meeting of the Division of
Plasma Physics

A−20

2005

S.P. Gerhardt, M. Inomoto, M.
American Physics Society, 47th
Stability Studies of Compact Toroid Plasmas
Yamada, H. Ji, A.J. Carver, A.
Annual Meeting of the Division of
in MRX
Kuritsyn, B. McGeehan, Y. Ren
Plasma Physics

Oct. 24–28, Denver, USA

2005-FP4-5

42

2005

M. Isobe, K. Toi1, H.
Matsushita, K. Goto, N.
Nakajima1, S. Yamamoto, S.
Murakami, A. Shimizu, C.
Suzuki, K. Nagaoka, Y.
Studies on fast ion transport induced by
9th IAEA Technical Meeting on
Yoshimura, T. Akiyama, T.
energetic particle modes using fast particle Energetic Particles in Magnetic
Minami, M. Nishiura, S.
diagnostics with high time resolution in CHS Confinement Systems
Nishimura, K. Matsuoka, S.
Okamura,D.S. Darrow, D.A. Spong, K.
Shinohara, M. Sasao and CHS
team

November 9 - 11, 2005, Takayama,Japan

2003-FP-2-4

43

2005

M. Yamada, H. Ji, S. Gerhardt,
Study of Two-Fluid Effects during Magnetic
M. Inomoto, R. Kulsrud, A.
Reconnection in a Laboratory Experiment
Kuritsyn, Y. Ren

American Physics Society, 47th
Annual Meeting of the Division of
Plasma Physics

Oct. 24–28, Denver, USA

2005-FP4-5

44

2005

E.V. Belova, R.C. Davidson, H. Three-dimensional Hall-MHD simulations of American Physics Society, 47thJi, M. Yamada, S.P. Gerhardt, counter-helicity spheromak merging andAnnual Meeting of the Division of
M. Inomoto
FRC formation
Plasma Physics

Oct. 24–28, Denver, USA

2005-FP4-5

45

2005

Y.Hasegawa, et al.

Wobble Motion Field Reversed
Configuration Plasmas

The American Physical Society
Division Plasma Physics

Oct. 24-28, Denver, USA

2004-FP5-37

46

2006

N. Ito, A. Mase, Y. Kogi et al.

Advanced Fabrication Method of Planar
Components for Plasma Diagnostics

The 16th International Toki
Conference

Dec. 5-8, 2006, Toki, Japan

2004-FP5-18

47

2006

N. C. Luhmann, Jr., C.W.
Domier, N. Ito, Y. Liang, A.
Mase, H. Park, E. Sakata, Z.
Shen, W. Tsai, Z. G.. Xia, Lu
Yang, P. Zhang

Advanced Microwave/Millimeter-Wave
Imaging Technology

The 16th International Toki
Conference

Dec. 5-8, 2006, Toki, Japan

2004-FP5-18

48

2006

H. Kiguchi, et. al.

Application of magnetized coaxial plasma
gun for external control of field revered
configuration

The American Physical Society
Division Plasma Physics

Oct.30-Nov.2, 2006, Philadelphia,USA

2006-FP2-3

49

2006

L. C. Steinhauer, T. Kanki, A.
IshidaComputation of Two-Fluid, Flowing
Equilibria

48th Annual Meeting of theDivision of Plasma Physics

Oct. 30-Nov. 3 2006, Philadelphia,USA

2006-FP2-7

50

2006

K. Yoshikawa, K. Masuda, T.
Takamatsu, S. Shiroya, T.
Misawa, Y. Takahashi, M.
Ohnishi, H. Osawa, E. Hotta
and K. Yamauchi

Current Status of Humanitarian Landmine
8th US-Japan Workshop on Inertial
Detection with a Compact Water-Cooled IEC
Electrostatic Confinement Fusion
DeviceMay 10-12, 2006, Osaka, Japan

2006-FP5-1

51

2006

K.Yamauchi, S.Ohura,D-D and D-3He Proton Measurements of
K.Nozaki, M.Watanabe,
Cylindrical Inertial Electrostatic Confinement 8th US-Japan IEC Workshop
A.Okino, T.Kohno and E.Hotta Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

52

2006

K.Yamauchi, S.Ohura,
K.Nozaki, M.Watanabe,
A.Okino, T.Kohno, E.Hotta,
and M.Yuura

June 4-8, 2006, Traverse City,
Michigan, USA

2006-FP5-1

53

2006

K. Masuda, S. Ohkawa, T.
Development of a Two-Dimensional CodeTakamatsu and K. Yoshikawa for Simulating IEC Discharges

May 10-12, 2006, Osaka, Japan

2006-FP5-1

54

2006

Y. Kogi, T. Sakoda, A. Mase et
The 16th International Toki
Development of ECE Imaging System on LHD
al.
Conference

Dec. 5-8, 2006, Toki, Japan

2004-FP5-18

55

2006

Development of Low-Loss Millimeter-Wave
The 2006 Asia-Pacific Microwave
N. Ito, A. Mase, N. Seko et al. Antennas on Fluorine Substrate Using
ConferenceElectro-Fine-Forming Fabrication

Dec. 13-15, 2006, Yokohama, Japan

2004-FP5-18

41

D-D and D-3He Proton Measurements of
33rd IEEE International
Cylindrical Radially Convergent Beam Fusion Conference on Plasma Science

8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

A−21

56

2006

H. Osawa, S. Yoshimura, T.
Tabata, M. Ohnishi

Discharge Characteristics of Anode Size in an 22nd Int. Symp. on Discharges andInertial Electrostatic Confinement Fusion
Electrical Insulation in Vacuum

Sep. 25-29, 2006, Matsue, Japan

2006-FP5-1

57

2006

K. Noborio, Y. Yamamoto, Y.
Ueno, S. Konishi

Evaluation of the Reaction Rate between
Beam Particles and Adsorbed Particles on
the Electrode of IECF Device

8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

58

2006

M. Yamada, Y. Ren, H. Ji, S.
Gerhardt, M. Inomoto, R.
Kulsrud, S. Dorfman

Experimental Study of Two-fluid Effects on
Magnetic Reconnection

American Physics Society, 48th
Annual Meeting of the Division of
Plasma Physics

Oct. 30–Nov. 3, Philadelphia, USA

2005-FP4-5

2006

M. Isobe, K. Toi, K. Nagaoka,
C. Suzuki, K. Goto, T. Akiyama,
T. Minami, S. Murakami, N.
Fast-ion-driven MHD instabilities andNakajima, S. Nishimura, M.
consequent fast ion losses in the compact
Nishiura, A. Shimizu, S.
helical system
Yamamoto, Y. Yoshimura, M.
Sasao, K. Matsuoka, S.
Okamura and D.A. Spong

21st IAEA Fusion Energy
Conference

Oct. 16-21, 2006, Chengdu, China

2003-FP-2-4

60

2006

J. W. Berkery, T. S. Pedersen,
J. P. Kremer, R. G. Lefrancois,
Q. R. Marksteiner, A. H.
First studies of pure electron plasmas in the The 8th International Workshop
Boozer, H. E. Mynicreiersen, Columbia Non-neutral Torus
on Non-Neutral Plasmas
F. Dahlgreen, H. Himura, and
X. Sarasola

June 16-20, 2006, Aarhus, Denmark

2005-FP5-17

61

2006

T. Ozaki, P. Goncharov, N.
Tamura et al.

January, 2006, Opole,Poland

2004-FP5-19

62

2006

D. Stutman, K. Tritz, L.
Delgado-Aparicio, M.
High throughput measurements of soft x-ray
Finkenthal, G. Suliman, L.
High Temperature Plasma
impurity emission using a multilayer mirror
Roquemore, R. Kaita, H.
Diagnostics
telescope
Kugel, D. Johnson, N. Tamura,
K. Sato, S. Sudo, C. Tarrio

May. 7-11, 2006, Williamsburg, USA

2006-FP5-22

63

2006

Highly Efficient Production of Excited
T. Nishi, K. Yoneda, K. Masuda
Neutral Helium Beams for Spectroscopic
and K. Yoshikawa
Diagnostics of Electric Fields in IEC Plasma

2nd JGSEE and Kyoto Joint
International Conference on
Sustainable Energy andEnvironment

Nov. 21-23, 2006, Bangkok, Thailand

2006-FP5-1

64

2006

Highly Efficient Production of Excited
T. Nishi, K. Yoneda, K. Masuda
Neutral Helium Beams for Spectroscopic
and K. Yoshikawa
Diagnostics of Electric Fields in IEC Plasma

8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

65

2006

H. Osawa, M. Ohnishi, T.
Furukawa, T. Suma, T.
Takamatsu, K. Masuda, K.
Yoshikawa

Improvement of Discharge Stability ofInertial electrostatic Confinement Fusion
DeviceSeventeenth American Nuclear
Society Topical Meeting on theTechnology of Fusion Energy

Nov. 12-15,
2006,Albuquerque,NM,USA

2006-FP5-1

66

2006

T. Takamatsu, T. Oishi, K.
Masuda and K. Yoshikawa

Improvement of Inertial Electrostatic
IEEE 22nd International
Confinement Device by Low Operating Gas
Symposium on Discharges andPressure using Magnetron- Discharge-BasedElectrical Insulation in Vacuum
Ion Source

Sept. 25-29, 2006, Matsue, Japan

2006-FP5-1

67

2006

A. Mase, Y. Kogi, N. Ito et al.

Int. Workshop on Microwave
Industrial Applications of Microwave Active
Devices, Systems and their
Diagnostics
Applications

Dec. 12-13 2006, Fukuoka, Japan

2004-FP5-18

68

2006

T. Fujimoto, T. Oishi, H. Zen,
Intensity Distribution of D-3He Fusion
T. Takamatsu, K. Masuda andReaction Rate in an IEC Device
K. Yoshikawa

IEEE/NPSS 22nd Symposium on
Fusion Engineering

Jun. 17-21, 2007, Albuquerque, NM,USA

2006-FP5-1

69

2006

Ion velocity measurements on NSTX using
S. PAUL, R. KAITA, A.L.
the SWIFT diagnostic
ROQUEMORE and N. NISHINO (Shifted Wavelength/lnterference Filter
Technique)APS-DPP06

Oct. 30–November 3 2006;
Philadelphia, Pennsylvania

2007-FP5-7

59

High Energy Particle Measurement using
International Conference on
Compact Neutral Particle Energy Analyzer in Research and Applications ofLarge Helical Device
Plasmas 2005

A−22

70

2006

K. Yoshikawa, K. Masuda, T.
Takamatsu, S. Shiroya, T.
Misawa, M. Ohnishi, H.
Osawa, E. Hotta and K.
Yamauchi71

2006

A. Mase, Y. Kogi, N. Ito et al.

Microwave Diagnostics

The 3rd Japan-Korea Seminar on
Advanced Diagnostics for SteadyState Fusion Plasma

Aug. 31-Sept. 3, 2006, Matsushima,Japan

2004-FP5-18

72

2006

H. Osawa, S. Yoshimura, M.
Ohnishi

Neutron Production of the IECF Device in
Different Size of Anode8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

73

2006

Y.Matsuzawa, et al.

Optical diagnostic System for Neural Particle The American Physical Society
Deensity of Field reversed Configuration
Division Plasma Physics

May 7-11, Williamburg, USA

2006-FP2-3

74

2006

M. Ohnishi, H. Osawa

Overview of IEC research in Kansai
University

8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

75

2006

O.Mitarai

Plasma current ramp-up and ignition in the
Component Test Facility (CTF)

US-Japan workshop

Jan. 24-25, 2006䠈University of Los
Angels (San Diego),USA

2006-FP2-6

76

2006

K.Nozaki, K.Yamauchi,
S.Ohura, M.Watanabe,
A.Okino, and E.Hotta

Preliminary Study of Beam-Beam Reactions 22nd Int. Symp. on Discharges andin IEC Fusion Device
Electrical Insulation in Vacuum

Sep. 25-29, 2006, Matsue, Japan

2006-FP5-1

77

2006

Progress in Microwave Diagnostics and
A. Mase, Y. Kogi, H. Hojo et al. Physics Issues in Magneticall Confined
PlasmasJul. 17-21, 2006, Tsukuba, Japan

2004-FP5-18

78

2006

Z. Shen, N. Ito, C.W. Domier,Protection Filters in ECEI Systems for Plasma The 16th International Toki
N.C. Luhmann, Jr., A. Mase, E.
Diagnostics
Conference
SakataDec. 5-8, 2006, Toki, Japan

2004-FP5-18

79

2006

T. Takamatsu, T. Oishi, S.
Ogawa, K. Masuda and K.
Yoshikawa

Recent R&D in IEC Neutron Source at Kyoto 8th US-Japan Workshop on Inertial
University
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

80

2006

T.Yamada, A. Ejiri,et al.

Reflectometry for Density Fluctuationand
Profile Measurements in TST-2

Dec. 5-8, 2006, Toki, Japan

2005-FP5-21

81

2006

A. Mase, Y. Yokota, K. Uchida Remote Experiment of Ultrashort-Pulse
et al.
Reflectometry on LHD

The 16th APS Topical Conference
on High Temperature Plasma
Diagnostics

May 7-12, 2006, Williamsburg, USA

2004-FP5-18

82

2006

Research and Development on a Compact
K. Yoshikawa, K. Masuda, Y.
Discharge-Based Fusion Neutron/Proton
Yamamoto and T. Takamatsu
Source for Advanced Technologies

3rd Symposium on Sustainable
Energy System

Aug. 30-Sept. 1, 2006, Kyoto, Japan

2006-FP5-1

83

2006

K. Yoshikawa, K. Masuda, T.
Takamatsu, S. Shiroya, T.
Misawa, Y. Takahashi, E.
Hotta, K. Yamauchi, M.
Ohnishi and H. Osawa

2nd JGSEE and Kyoto Joint
International Conference on
Sustainable Energy andEnvironment

Nov. 21-23, 2006, Bangkok, Thailand

2006-FP5-1

84

2006

Simultaneous Measurements of Neutrons
K. Masuda, S. Ogawa, T.
and Energetic Protons from D-D and D-3He
Takamatsu and K. Yoshikawa Fusion Reactions in an Inertial Electrostatic
Confinement Device

IEEE 22nd International
Symposium on Discharges andElectrical Insulation in Vacuum

Sept. 25-29, 2006, Matsue, Japan

2006-FP5-1

85

2006

T. Oishi, S. Ogawa, T.
Spatial Distribution of D-3He Advanced
Takamatsu, H. Zen, K. Masuda Fuels Fusion Reactions in an Inertial
and K. Yoshikawa
Electrostatic Confinement Device

8th US-Japan Workshop on Inertial
Electrostatic Confinement Fusion

May 10-12, 2006, Osaka, Japan

2006-FP5-1

86

2006

K. Masuda, K. Yoshikawa, T.
Ohishi, S. Ogawa, H. Zen and
T. Takamatsu

Oct, 16-21, 2006, Chengdu, China

2006-FP5-1

Landmine detection by a compact fusion
neutron source

International Workshop on "Humanitarian Landmine Detection
and Detection of Illicit Materials"

Mar. 7-9, 2007, Kyoto, Japan

2006-FP5-1

The 6th International Conference
on Open Magnetic Systems for
Plasma Confinement

16th Internat. Toki Conf.

Research and Development on a Compact
Discharge-Driven D-D Fusion Neutron
Source for Explosive Detection

Spatial Distribution of D-D/D-3He Advanced
21st IAEA Fusion Energy
Fuels Fusion Reactions in an Inertial
ConferenceElectrostatic Confinement Device

A−23

87

2006

Status and Prospect of Inertial Electrostatic
Eiki Hotta and Tokyo Tech IEC
Confinement Devices as Neutron/Proton
Group
Sources

The 3rd International Symposiumon Sustainable Energy System

Aug, 30–Sep. 1, 2006, Kyoto, Japan

2006-FP5-1

88

2006

S.P. Gerhardt, M. Inomoto, E. Studies of Equilibrium and Stability of
Oblate FRCs in the Magnetic Reconnection
Belova, M. Yamada, H. Ji, Y.
ExperimentRen, S. Dorfman, E. Martin

American Physics Society, 48th
Annual Meeting of the Division of
Plasma Physics

Oct. 30–Nov. 3, Philadelphia, USA

2005-FP4-5

89

2006

S.P. Gerhardt, M. Inomoto,Studies of Free-Boundary Field-reversed
E.V. Belova, M. Yamada, H. Ji, Configurations with Improved Stability in
Y. Renthe Magnetic Reconnection Experiment

21st IAEA Fusion Energy
Conference

Oct. 16-21, 2006, Chengdu, China

2005-FP4-5

90

2006

K. Saito, S. Murakami, M.
Osakabe, M.Nishimura,
T.Seki, T.Ozaki et al.

Study of High-energy Ion Tail Formation
IAEA Fusion Energy conferencewith Second Harmonic ICRF Heating and NBI
2006
in LHD

October, 2006, IAEA-CN-149, EX/P617

2004-FP5-19

91

2006

Kanamaru, et al.

Tilt instabilty at formation phase

The American Physical Society
Division Plasma Physics

Oct.30-Nov.2, Philadelphia

2006-FP2-3

92

2006

Y. OnoTransient and Intermittent Magnetic
Reconnections in TS-3/4 Merging
Experimentsand Their Extension to UTST
High-Beta ST Experiment

Petschek Memorial Conference

March 2006, College Park, Maryland,USA

2005-FP2-4

93

2006

Y. OnoUS/Japan Cooperation in Fusion Energy
Research

2006 US/Japan Workshop on
Compact Torus Plasmas, The Roleof Flow in Compact Torus Plasmas

Nov. 2-4, 2006, , Swarthmore
College PA, USA

2006-FP4-5

94

2007

20 GHz to 40 GHz Beam Shaping/Steering
L. Yang, N. Ito, C. W. Domier,
Phased Antenna Array System using Fermi
N. C. Luhmann, Jr., A Mase
Tapered Slot Antenna

The IEEE MTT-S International
Microwave Symposium

Jun. 3-8, 2007, Honolulu, USA

2004-FP5-18

95

2007

Z. Shen, C. W. Domier, N. C.
Luhmann, Jr. N. Ito, A. Mase,
A. J. H. Donne,
H. Park

2-D Passive Millimeter wave Imaging System The 2007 Asia Pacific Microwave
for Plasma Diagnostics
ConerenceDec. 11-14, 2007, Bangkok, Thailand

2007-FP5-6

96

2007

K. Yoshikawa, K. Masuda, T.
Takamatsu, S. Shiroya, T.
Misawa, Y. Takahashi, E.
Hotta,K. Yamauch, M.
Ohnishi, H. Osawa

Anti-Personnel Landmine Detection by Useof an IEC Neutron Source

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

97

2007

M.Ohnishi, Y. Tsuji, N.
Yoshida, H. Osawa

Characteristics in Pulse Operation of IEC
Device with Confronting Two Plasma
Sources

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

98

2007

T. Oosako, et al.

Combline Antenna for Lower Hybrid Current
Korea-Japan workshop on heating
Start-up Experiments in Tokyo Spherical
technology of Fusion plasmas
Tokamak-2

Oct.16-17, 2007, Jeju, Korea

2005-FT3-2
2006-FT3-2

99

2007

Y. OnoCurrent Sheet Dynamics in TS-3 and TS-4
Tokamak Reconnection Experiments

The 9th International Workshop
on the Interrelationship between
Plasma Experiments in Laboratory
and SpaceAug. 2007, Palm Cove Resort,Cairns, Australia

2007-FP3-2

100

2007

Y. Ono , Y. Hayashi, H.
Imanaka and R. Imazawa:

Current Sheet Dynamics in TS-4 Tokamak
Reconnection Experiment

50th Annual Meeting of theDivision of Plasma Physics, APS

Nov. 2007, Orland, FL, USA

2007-FP3-2

101

2007

Z. Shen, N. Ito, E. Sakata, C.
D-Band Double Dipole Antenna for Use in
W. Domier, N. C. Luhmann, Jr.
Millimeter Wave Imaging Systems
A. MaseThe 2007 IEEE International
Symposium on Antenna andPropagation

Jun. 9-15, 2007, Honolulu USA

2004-FP5-18

102

2007

K.Tomiyasu and E.Hotta

The Second MIT-Tokyo Tech
Design for Medical Radioisotope Production
Symp. on Innovative Nuclear
Using a Compact Fusion Proton Source
Energy System (TM-INES2)

Jul. 2007, Kamakura, Japan

2006-FP5-1

103

2007

N.Yoshida, Y. Tusji, H. Osawa, Development of Fast Numerical Code Based 9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
M. Ohnishion Direct Interaction of Charged Particles
Electrostatic Confinement Fusion

A−24

2006-FP5-1

A. Mase, Y. Kogi, N. Ito et al.

Development of Microwave Diagnostic
Systems and their Application

U.S.-Japan Workshop on
Millimeter-Wave Plasma
Diagnostics

2007

N. Ito, A. Mase, Y. Kogi et al.

Development of Planar Components Using
Advanced Fabrication

The Joint 32nd International
Conference on Infrared andMillimeter Waves and 15th
International Conference on
Terahertz Electronics

106

2007

K. Masuda, K. Yoshikawa, T.
Misawa, K. Yamauchi, Y.
Takahashi, S. Shiroya, E.
Hotta, M. Ohnishi and H.
Osawa

Directional detection of nitrogen andhydrogen in explosives by use of a DDfusion-driven thermal neutron source

NATO Advanced ResearchWorkshop on “Detection of Liquid
Explosives and Flammable Agentsin Connection with Terrorist
Actions”

107

2007

H. Osawa, N. Yoshida, M.
Ohnishi

FDTD Simulation on RF Ion Source for IEC

108

2007

Tetsuo OZAKI, Pavel
R.GONCHAROV, Evgeny
VESHCHEV, et al.

Helium ion observation during 3rd harmonic
International Toki Conference
ion cyclotron heating in Large Helical Device

109

2007

T.Ozaki, P.Goncharov,Helium measurements simulating alphaE.Veschev, S.Sudo, N.Tamura, particle diagnostics by the pellet charge
et al.
exchange in Large Helical Device

Proc. of INTERNATIONAL
WORKSHOP ON BURNING
PLASMA DIAGNOSTICS

110

2007

H. Horibe, M. Ohnishi, H.
Osawa

111

2007

Y.Tsujii, N. Yoshida, H. Osawa,
IEC Research of Kansai University
M. Ohnishi

112

2007

N. Tamura, K. Sato, H.
Funaba, S. Sudo, K. Tritz, D.
Stutman, L. Delgado-Aparicio, Impact of a tracer-encapsulated solid pellet 13th International Workshop on
M. Finkenthal, H. Kugel, R.
injection on NSTX plasmas
Spherical Torus
Kaita, L. Roquemore, M. Bell,
V. Soukhanovskii

113

2007

T. Fujimoto, T. Oishi, H. Zen,
Intensity Distribution of D-3He Fusion
T. Takamatsu, K. Masuda andreaction Rate in an IEC Device
K. Yoshikawa

114

2007

Y. Takase, et al.

115

2007

116

104

105

2007

High Voltage Pulse Modulator

Feb. 25-27, 2008, UC Davis, USA

2007-FP5-6

Sept. 2-7, 2007, Cardiff, U.K.

2007-FP5-6

Oct. 17-19, 2007, Saint-Petersburg,
Russia2006-FP5-1

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

Oct. 16-19, 2007, Toki, Japan

2004-FP5-19

September 24 - 28, 2007, Varenna,
Italy

2004-FP5-19

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

Oct. 10-12, 2007, Fukuoka, Japan

2007-FP5-15

9th US-Japan Workshop on Inertial
May 22-24, 2007, Argonne, IL, USA
Electrostatic Confinement Fusion

2006-FP5-1

LHCD Scenarios for Spherical Tokamak
Plasmas17th Top. Conf. on Radio
Frequency Power in Plasmas
Clearwater, 2007

May 7-9, 2007, Clearwater, Florida,USA

2006-FP4-4

K.Yamauchi, K.Nozaki,
M.Watanabe, A.Okino and
E.Hotta

Low Pressure IECF Operation Using
Differentially-Pumped Ion Sources

9th US-Japan IEC Workshop on
Small Plasma and Accelerator
Neutron Sources

May 22-24, 2007 Argonne, USA

2006-FP5-1

2007

A. Mase, Y. Kogi, N. Ito et al.

Microwave Imaging for Plasma Diagnostics
and Its Applications

The 13th International Symposium
Sept. 18-21, 2007, Takayama, Japanon Laser-Aided Plasma Diagnostics

2007-FP5-6

117

2007

A. Sanpei, S. Masamune, R.
Ikezoe, et al.

Neoclassical RFP equilibria with reactor
regime parameters

12th IEA/RFP Workshop

2006-FP2-8

118

2007

A. Ishida, L.C. Steinhauer, Y.- Numerical computation for two-fluid MHD
K. M. Pengequilibria with flow

119

2007

K.Yamauchi, K.Tomiyasu,
M.Watanabe, A.Okino and
E.Hotta

9th US-Japan IEC Workshop on
Overview of IECF Research at Tokyo Institute
Small Plasma and Acceleratorof Technology
Neutron Sources

120

2007

T. Kanki, L. C. Steinhauer, M.
NagataPartially Relaxed Two-Fluid Flowing
Equilibria in Helicity-Driven Spherical Tours

Mar 26-28, 2007, Kyoto, JapanThe 13th International Workshop
October 10-12, 2007, Fukuoka, Japanon Spherical Tori 2007

US-Japan Workshop on Innovative
Active Control for High
Performance Confinement ofCompact Toroid

A−25

2006-FP2-4

May 22-24, 2007, Argonne, USA

2006-FP5-1

Sep. 18-20 2007, Tokyo, Japan

2006-FP2-7

2007

2nd Research Coordination
Research and Development of a Compact
Meeting of the IAEA’s CoordinatedK. Yoshikawa, S. Shiroya, E.
Discharge-Driven D-D Fusion Neutron
Research Project on “Neutron
Hotta, M. Ohnishi, T. Misawa
Source And Advanced Gamma-ray Detection Based Techniques for theand K. Masuda
System for the Detection of Explosives
Detection of Illicit Materials andExplosives”

Nov. 12-16, 2007, Mumbai, India

2006-FP5-1

2007

K. Yoshikawa, K. Masuda, T.
Misawa, T. Takamatsu, K.
Yamauchi, Y. Takahashi, S.
Shiroya, E. Hotta, M. Ohnishi
and H. Osawa

Apr. 9-13, 2007, Orlando, Florida,USA

2006-FP5-1

123

2007

T. Misawa, K. Yoshikawa, K.
Masuda, T. Takamatsu, T.
Fujimoto, K. Yamauchi, E.
Research and Development of Landmine
Hotta, Y. Takahashi, T. Yagi, Y.
Detection System using a Compact Fusion
Yamamoto, S. Shiroya, M.
NeutronOhnishi, H. Osawa, Y. Kubo,
M. Tabei, Y. Sugihara and T.
Doi

IAEA Technical Meeting on Use of
Combined Devices for
Humanitarian Demining andExplosives Detection

Nov. 26-30, 2007, Vienna, Austria

2006-FP5-1

124

2007

Y. OnoTransient and Explosive Magnetic
Reconnections in TS-3 and 4 Merging
Experiments

The US-Japan Symposium on
Plasma Merging and Magnetic
Reconnection

Mar. 2007 St. Michael MD, USA

2007-FP3-2

125

2007

Y. OnoTransient and Intermittent Magnetic
Reconnections in TS-3 Spherical Tokamak
Merging Experiment

National Cheng Kung University
Symposium

Jan. 4-7, 2007, Tainan, Taiwan

2007-FP3-2

Joint Conference of the 17th
International Toki Conference on
Physics of Flows and Turbulence in
Plasmas and the16th International
Stellarator/Heliotron Workshop
2007

15-19 Oct. 2007, Toki, Japan

2006-FP2-7

The Joint 32nd International
Conference on Infrared andMillimeter Waves and 15th
International Conference on
Terahertz Electronics

Sept. 2-7, 2007, Cardiff, U.K.

2007-FP5-6

121

122

Research and Development of Humanitarian
SPIE Defense and Security
Landmine Detection System by a Compact
Symposium
Discharge-Type Fusion Neutron Source

2007

T. Kanki, L. C. Steinhauer, M.
NagataTwo-Fluid Flowing Equilibria of Helicity
Injected Spherical Torus with Non-Uniform
Density

127

2007

Z. Shen, N. Ito, Z. Xia, C. W.
Domier, A. Mase, and N. C.
Luhmann, Jr.

Wide Bandwidth Mixer Array Developmentin Millimeter Wave Imaging Systems for
Plasma Diagnostics

128

2007

P. Zhang, C. W. Domier, Z.
Shen, N. C. Luhmann, Jr., H. K. Wideband ECEI Upgrade for Increased
Park, A. J. H. Donne, N. Ito, A. Plasma Coverage
Mase

129

2008

A. Mase, Y. Kogi, N. Ito et al.

130

2008

A. Mase, Y. Kogi, N. Ito et al.

131

2008

132

133

126

The 13th International Symposium
Sept. 18-21, 2007, Takayama, Japanon Laser-Aided Plasma Diagnostics

2007-FP5-6

Advancement of Microwave/ MillimeterWave Diagnostics in Magnetically Confined
PlasmaThe 2008 Int. Workshop on
Frontiers in Space and Fusion
Energy Sciences

Nov. 6-8, 2008, Tainan, Taiwan

2007-FP5-6

Advancements of Microwave Diagnostics
and Their Applications

The 11th IEEE International
Conference on Communication
Technology

Nov. 10-12, 2008, Hangzhou, PR
China

2007-FP5-6

A. Sanpei, K. Oki, R. Ikezoe, et Characterization of equilibria in a lowal.
aspect-ratio RFP

ICPP2008

Sep. 8-12, 2008, Fukuoka, Japan

2006-FP2-8

2008

T.Ozaki, Pavel R. Goncharov,Evgeny A. Veshchev, Shigeru Comparison of neutral particle flux decay
Sudo, Tsuguhiro Watanabe, times on the NBI plasmas in Large Helical
High-Energy Particle Group
Deviceand LHD Experimental GroupInternational Toki Conference

2008.12.9-12 Toki, Japan

2004-FP5-19

2008

R. Raman, B.A. Nelson,…,M.
Nagata,…, et al.

The 4th IAEA Technical Meetingon Spherical Tori and 14th
International Workshop on
Spherical Torus

Oct. 7-10, 2008, Roma, Italy

2006-FP4-3
2007-FP3-5

Coupling solenoid-free Coaxial Helicity
Injection started discharges to induction in
NSTX

A−26

10th US-Japan Workshop on
Development of a Coaxial Double Cylindrical
Inertial Electrostatic Confinement
Inertial Electrostatic Confinement Device
Fusion134

2008

K.Yokoyama, K.Tomiyasu,
M.Watanabe and E.Hotta

135

2008

T. Nakagawa, K. Masuda, T.
Development of an IEC Device Driven by a
Kajiwara, H. Zen, K. Yoshikawa Magnetron Ion Source for Low Pressure
and K. Nagasaki
Operation

136

2008

N. Ito, A. Mase, Y. Kogi et al.

Development of Planar Devices Using LowLoss Materials

137

2008

138

Dec. 2008, Kyoto, Japan

2008-FP5-8

10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

The 11th IEEE International
Conference on Communication
Technology

Nov. 10-12, 2008, Hangzhou, PR
China

2007-FP5-6

Development of Ultrashort-Pulse
Y. Yokota, A. Mase, Y. Kogi etReflectometry for Density Profileal.
Measurement in LHD

The International Congree on
Plasma Physics 2008

Sept. 8-12, 2008, Fukuoka, Japan

2007-FP5-6

2008

T. Kajiwara, K. Masuda, T.
Nakagawa, H. Zen and K.
Nagasaki

Double-grid IEC for Energy Recovery from
Escaping Electron Beams

10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

139

2008

K.Tomiyasu, K.Yokoyama,
M.Watanabe, A.Okino and
E.Hotta

Effects of Cusp Magnetic Field in a
18th Topical Mtg. on the
Cylindrical Radially Convergent Beam Fusion
Technology of Fusion Energy
DeviceSep. 2008, California, USA

2008-FP5-8

140

2008

K. Noborio, T. Kanagae, Y.
Yamamoto, S. Konishi

10th US-Japan Workshop on
Generation of Neutron Beam by theInertial Electrostatic Confinement
Cylindrical Fusion Neutron Source -Designing by using MCNP Transport Code -- Fusion

Dec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

141

2008

Y.Yamamoto, A. Ishidou, K.
Noborio, S. Konishi

Generation of Neutron Beam by the
Cylindrical Fusion Neutron Source -Objective and Targets --10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

142

2008

H. Horibe, M. Ohnishi, H.
Osawa

High Voltage Power Supply -some plasma
pllications-10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

143

2008

Multi-fluid MHD equilibria for ST plasmas
A. Ishida, L.C. Steinhauer, Y.with near-sonic flow and reduced trapped
K. M. Pengion fraction

35th EPS Plasma Physics Meeting

9-13 June, 2008, Hersonissos, Crete,
Greece2008-FP3-6

144

2008

A. Sanpei, S. Masamune, R.
Ikezoe, et al.

Neoclassical Equilibrium in a Low-Aspect
Ratio RFP Machine RELAX

35th EPS Meeting

June 9-13, 2008, Hersonissos, Greek

2006-FP2-8

145

2008

M. Inomoto, Y. Ono

Nonlinear mode couplings in linear plasmas

The US-Japan Workshop on
Magnetic Reconnection 2008,

Mar. 2008. 52, Okinawa, Japan

2008-FP3-1

146

2008

K. Masuda, Y. Yamamoto, K.
Noborio, T. Nakagawa, T.
Kajiwara, H. Zen, K. Nagasaki
and K. Yoshikawa

Overview of IEC Research at Kyoto
University

10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

147

2008

K.Tomiyasu, K.Yokoyama,
M.Watanabe, and E.Hotta

10th US-Japan Workshop on
Particle-in-Cell Simulation of Magnetic-assist
Inertial Electrostatic Confinement
Electrostatic Confinement Fusion
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

148

2008

T.Ozaki, P.Goncharov,
E.Veshchev, N.Tamura,
Pellet charge exchange helium
S.Sudo, T.Seki, H.Kasahara,High Temperature Plasmameasurement using neutral particle analyzer
high Energy Particle Groupe,
Diagnostics
in Large Helical Device
Wave Heating Group and LHD
Experimental GroupMay 11-15, 2008, Albuquerque, NM,USA

2004-FP5-19

149

2008

K. Sakuraba,et al.

Plasma Dynamics in Translation Process of
Field Reversed Configuration

Nov. 12-16,Orland, USA

2007-FP3-1

The American Physical Society
Division Plasma Physics

A−27

150

2008

Tetsuo OZAKI, Pavel
R.GONCHAROV, Evgeny
VESHCHEV, Naoki TAMURA,
Shigeru SUDO, Tetsuo SEKI,
Hiroshi KASAHARA, HighEnergy Particle Group

151

2008

Y. OnoRecent Progress in TS-4 and UTST ST
Merging

152

2008

Y. Ono, Toru Ii, Y. Hayamshi,
T. Yamada. M. Inomoto

Recent Progress of TS-4 Magnetic
Reconnection Experiment

153

2008

154

Radial Profiles of High-Energy Particles in
NBI and ICH Plasmas Measured by Pellet
ICPP
Charge Exchange Technique on Large Helical
DeviceSep. 8-12, 2008 Fukuoka, Japan

2004-FP5-19

51st Annual Meeting of theDivision of Plasma Physics, APS

Nov. 2008, Dallas, TX, USA

2008-FP3-1

The First International Workshop
on "Frontiers In Space and Fusion
Energy Sciences

Nov. 2008. Tainan, Taiwan

2008-FP3-1

H. Himura, K. Nakamura, D.
Recent progress on toroidal nonneutral
Sugimoto, A. Sanpei, S.
plasmas confined on heliotron magnetic
Masamune, M. Isobe, F. Sano surfaces

The 9th International Workshop
on Non-Neutral Plasmas

June. 16-20, 2008, NY, USA

2008-FP4-2

2008

Y. Yokota, A. Mase, Y. Kogi et Reconstruction of Edge Density Profiles onal.
LHD Using Ultrashort-Pulse Reflectometry

The 17th APS Topical Conference
on High-Temperature Plasma
Diagnostics

May 11-15, 2008, Albuquerque, USA

2007-FP5-6

155

2008

Simulation Study and Experiment of Breast
S. Takaichi, A. Mase, Y. Kogi et
The 2008 Asia Pacific Microwave
Cancer Detection Using an Ultrashort-Pulse
al.
Conference
Radar

Dec. 16-19, 2008, Hong Kong, China

2007-FP5-6

156

2008

R. Raman, T.R. Jarboe, M.
Nagata, et al.

Oct. 13-18, 2008, Geneva, Swiss

2006-FP4-3
2007-FP3-5

157

2008

N. NISHINO, S. PAUL, R. KAITA Status of Two-Dimensional Ion Velocity
and A.L. ROQUEMORE
Measurement System in NSTX

Int. Conference of Plamsa Physics
2008

Sep. 8-12, 2008, Fukuoka, Japan

2008-FP5-4-2007-FP5-7

158

2008

Q. R. Marksteiner, T. S.
Pedersen, J. W. Berkery, M. S.
Hahn, J. M. Mendez, B. D. de Studies of a parallel force balance breaking
Gevigney, P. Ennever, D.
instability in a stellarator
Boyle, M Shulman, and H.
HimuraThe 9th International Workshop
on Non-Neutral Plasmas

June. 16-20, 2008, NY, USA

2008-FP4-2

159

2008

H. Osawa, T. Miyashita, K.
Kitagawa, M. Ohnishi

Two Ion Sources Operation on Inertial
Electrostatic Confinement Fusion Device

10th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionDec. 9-11, 2008, Kyoto, Japan

2008-FP5-8

160

2008

T. Kanki, L. C. Steinhauer, M.
NagataTwo-Fluid Flowing Equilibria of Spherical
49th Annual Meeting of theTorus Sustained by Coaxial Helicity Injection Division of Plasma Physics

Nov. 12-16, 2007, Orlando, USA

2006-FP2-7

161

2008

Y. Yokota, A. Mase, Y. Kogi et Ultra-Wide Band Radar Reflectometer foral.
Measurement of Plasma Density Profiles

The 11th IEEE International
Conference on Communication
Technology

Nov. 10-12, 2008, Hangzhou, PR
China

2007-FP5-6

162

2009

Y. Ono2009 US - Japan Workshop on
Reconnection

Oct. 5 - 7 2009, Madison, WI, USA

2009-FP4-1

163

2009

K. Masuda, T. Nakagawa, T.
An Inertial Electrostatic Confinement Fusion
2nd Int. Conf. on Microelectronics
Kajiwara, K. Yoshikawa and K. Device Driven by a Built-In Ring-Shaped Ion
and Plasma Technology
Nagasaki
Source in Low Pressure Regime

Sep. 2009, Busan, Korea

2008-FP5-8

164

2009

T. Ozaki, M. Koga, H. Shiraga,
Calibration of the compact electron
R. Kato, S. Kashiwagi, G.
ITC19
spectrometer for FIREX-I project in Gekko XII
Isoyama, H. Sakagami and
FIREX group

Dec. 8-11, 2009 Toki, Japan

2004-FP5-19

165

2009

T. Yamamoto, Y. Nagayama,
H. Nakanishi, et al.

Jun. 15-19, 2009, Aix-en-Provence,France2008-FP5-7

166

2009

T. Ozaki, M. Koga, H. Shiraga, DEVELOPMENT OF THE COMPACT
Inertial Fusion Science andH. Azechi, H. Sakagami and
ELECTRON SPECTROMETER FOR THE FIREX-I
Application
FIREX GroupPROJECT IN GEKKO XII

Sep 6-11, 2009 San Francisco, CA

2004-FP5-19

Solenoid-free Plasma Start-up in NSTX using The 22nd IAEA Fusion Energy
Transient CHI
Conference

3-D Fast Reconnection in TS-3 and 4
Merging Experiments

Configuration of the Virtual Laboratory for
Fusion Researches in Japan

7th IAEA Technical Meeting onControl, Data Acquisition, andRemote Participation for Fusion
Research

A−28

167

2009

K. Tomiyasu, K. Yokoyama, M.
Discharge Characteristics of MagneticWatanabe, A. Okino and E.
assisted Electrostatic Confinement Device
Hotta

2nd Int. Conf. on Microelectronics
and Plasma Technology

Sep. 2009, Busan, Korea

2008-FP5-8

168

2009

T. Kajiwara, K. Masuda, K.
Yoshikawa and K. Nagasaki

Double-grid IEC for Energy Recovery from
Escaping Electron Beams

2nd International Conference on
Microelectronics and Plasma
Technology

Sept. 23-25, 2009, Busan, Korea

2008-FP5-8

169

2009

T. Kajiwara, K. Masuda, J.
Kipritidis and K. Nagasaki

11th US-Japan Workshop on
Double-grid IEC for Recovery of Energy from
Inertial Electrostatic Confinement
Escaping Electron Beams
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

170

2009

K. Kitagawa, T. Miyashita, A.
Maeda, I. Nakano, H. Osawa, Drawing Out Electrode of Ion Beam for IEC
M. Ohnishi

11th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

171

2009

M. Isobe, K. Ogawa, K. Toi, M. Effect of energetic-ion-driven MHD
Osakabe, K. Nagaoka, A.
instabilities on energetic-ion-transport in
Shimizu, D.A. Spong, CHS and Compact Helical System and Large Helical
LHD experiment groups
Device17th International
Stellarator/Heliotron Workshop

Oct. 12-16, 2009, Princeton, New
Jersey, USA

2003-FP-2-4

172

2009

K.Tomiyasu, K.Yokoyama,
Y.Jinushi, M.Watanabe, andE.Hotta

Experimental Study of Magnetic-Assisted
Electrostatic Confinement

11th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionOct.12-14, 2009, Madison, WI, USA

2009-FP5-1

173

2009

T. Hochin, Y. Yamauchi, H.
Nomiya, H. Nakanishi, M.
KojimaFast Subsequence Matching in
PlasmaWaveform Databases

5th International Conference onIntelligent Information Hiding andMultimedia Signal Processing(IIHMSP2009)

Sep. 12-14, 2009, Kyoto, Japan

2004-FP5-39

174

2009

K. Noborio, T. Kanagae, Y.
Yamamoto, S. Konishi

Generation of Sharp and Thermalized
Neutron Beam using Cylindrical Fusion
Neutron Source

11th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

175

2009

A. Maeda, T. Miyashita, K.
Kitagawa, I. Nakano, H.
Osawa, M. OhnishiHigh Current Operation on IEC

11th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

176

2009

T. Hochin, Y. Yamauchi, H.
Nakanishi, M. Kojima, H.
NomiyaIndexing of Plasma Waveforms for
Accelerating Search and Retrieval of Their
Subsequences

7th IAEA Technical Meeting onControl, Data Acquisition, andRemote Participation for Fusion
Research

Jun. 15-19, 2009, Aix-en-Provence,France2004-FP5-39

177

2009

H. Nakanishi, T. Yamamoto,
M. Emoto, Y. Nagayama, K.
Kawahata, et al.

LABCOM/X Experiment Data Platform andFusion Virtual Laboratory in Japan

7th IAEA Technical Meeting onControl, Data Acquisition, andRemote Participation for Fusion
Research

Jun. 15-19, 2009, Aix-en-Provence,France2008-FP5-7

178

2009

K.Yokoyama, Y.Jinushi,
Neutron Flux Distribution in a Coaxial
K.Tomiyasu, M.Watanabe andDouble Cylindrical Device
E.Hotta

11th US-Japan Workshop on
Inertial Electrostatic Confinement
FusionOct.12-14, 2009, Madison, WI, USA

2009-FP5-1

179

2009

Neutron Production with Confronting Ion
H. Osawa, T. Miyashita, A.
Sources on Inertial Electrostatic
Maeda, I. Nakano, M. Ohnishi
Confinement Fusion Device

2nd Int. Conf. on Microelectronics
and Plasma Technology

Sep. 2009, Busan, Korea

2008-FP5-8

180

2009

Optical diagnostics and numerical modeling 11th US-Japan Workshop on
J. Kipritidis, J. Khachan and K.
of a gaseous discharge Inertial Electrostatic Inertial Electrostatic Confinement
MasudaConfinement device
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

181

2009

K. Masuda, J. Kipritidis, T.
Kajiwara, T. Nakagawa, K.
Nagasaki, Y. Yamamoto, K.
Noborio and T. Kanagae

Overview of Kyoto University Research and 11th US-Japan Workshop on
Considerations for an IEC Device Driven by a Inertial Electrostatic Confinement
Built-In Ring-Shaped Ion Source
FusionOct. 12-13, 2009, Madison,
Wisconsin, USA

2009-FP5-1

182

2009

Y. OnoPhysics and applications of impulsive 3-D
magnetic reconnection

Nov. 30-Dec. 3, 2009, Tainan, Taiwan

2009-FP4-1

2009 International Workshop on
Frontiers In Space and Fusion
Energy Sciences (2009 FISFES)

A−29

183

2009

Y. Haraguchi, H. Hojo, Y. Ishii
et al.

Preliminary Simulation Study for Microwave The 19th International Toki
Imaging Reflectometry
Conference (ITC-19)

184

2009

A. Mase, N. Ito, D. Zhang et al.

The 2009 International Workshop
Progress in Microwave Diagnostics and theiron Frontiers in Space and Fusion Nov. 30-Dec. 3, 2009, Tainan, Taiwan
Applications
Energy Sciences

2009-FP5-2

185

2009

A. Mase, Y. Kogi, N. Ito et al.

Progress in Microwave Diagnostics Related
to LHD Collaborative Research

Feb. 2-5, 2009, Murramarang,
Australia

2007-FP5-6

186

2009

T. Yamamoto, Y. Nagayama,
H. Nakanishi, et al.

12th International Conference on
Progress of the Virtual Laboratory for Fusion Accelerator and Large
Researches in Japan
Experimental Physics Control
Systems (ICALEPCS2009)

Oct. 12-16, 2009, Kobe, Japan

2008-FP5-7

187

2009

Y. Yokota, A. Mase Y. Kogi etal.

Reconstruction Method of X-Mode
Ultrashort-Pulse Reflectometry in LHD

The 14th International Symposiumon Laser Aided Plasma Diagnostics

Sept. 21-24, Castelbrando, Italy

2009-FP5-2

188

2009

Y. Takase, et al.

RF Experiments on TST-2

51st Annual Meeting of APS/DPP

Nov. 2-6, 2009, Atlanta, Georgia

2009-FP2-4

189

2009

K. Akaki, A. Mase, Y. Kogi etal.

Study of Dual-Dipole Antenna Array for
Millimeter Wave Imaging

The. 34th Int. Conf. on Infrared,
Millimeter, and Terahertz Wave

Sept. 11-15, 2009, Busan, Korea

2009-FP5-2

190

2009

J.A. Stillerman, W. Burke, B.
Labombard

12th International Conference on
Sub-sample Time-base Resolution in a
Accelerator and Large
Heterogeneous Distributed Data Acquisition
Experimental Physics Control
Environment
Systems (ICALEPCS2009)

Oct. 12-16, 2009, Kobe, Japan

2009-FP5-13

191

2009

Y. OnoUS-Japan Workshop on Physics ofThree dimensional magnetic reconnection in
Plasma Merging and Magnetic
torus plasma merging experiments
Reconnection

Mar. 2-4, 2009, Princeton, NJ, USA

2009-FP4-1

192

2009

H. Horibe, M. Ohnishi, H.
Osawa

Useful Information for High Voltage Power
Supply2nd International Conference on
Microelectronics and Plasma
Technology

Sept. 23-25, 2009, Busan, Korea

2008-FP5-8

193

2010

A. Mase, N. Ito, D. Zhang et al.

International Workshop on
Application of Microwave Diagnostic
Microwave Devices, Systems, andSystems to Medical and Assisted Technology
their Applications 2010

Mar. 16-17, 2010, Fukuoka, Japan

2009-FP5-2

Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

4424 (2000) 37-44

2000-FP5-18

88 (2000) 2943-2947

2000-FP5-18

The 8th Japan-Australia Plasma
Diagnostics Workshop

Dec. 8-11, 2009, Toki, Japan

2009-FP5-2

3.4.5HighEnergyDensityScience
1.JournalPaper
No

1

2

Year

Authors

Title of Paper

Journal2000

K. Fujita, A. Sunahara, K.A.
Tanaka, N. Isumi, T. Jitsuno,
N. Miyanaga, T. Miyakoshi, H.
Otani, M. Fukao, H. Heya, Y. Model experiments of fast ignition with
Ochi, Y. Kitagawa, R. Kodama, coaxial high-power laser beams
K. Mima, H. Nishimura, T.
Norimatsu, Y. Sentoku, H.
Takane, T. Yamanaka

2000

T. Kadono, M. Yoshida, E.
Takahashi, I. Matsushima, Y.
Flyer acceleration by a high-power KrF laser
Owadano, N. Ozaki, K. Fujita,
Journal of Applied Physics
with a long pulse duration
M. Nakano, K.A. Tanaka, H.
Takenaka and K. Kondo

SPIE

A−30

2000

K.A. Tanaka, M.M. Allen, A.
Pukhov, R. Kodama, H. Fujita,
Y. Kato, T. Kawasaki, Y.
Evidence of relativistic laser beam
Kitagawa, K. Mima, N. Morio, filamentation in back-reflected images
H. Shiraga, M. Iwata, T.
Miyakoshi, and T. Yamanaka

Phys. Rev. E

62 (2000) 2672-2677

2000-FP5-18

2000

K.A. Tanaka, R. Kodama, H.
Fujita, M. Heya, N. Izumi, Y.
Kato, Y. Kitagawa, K. Mima, N.
Miyanaga, T. Norimatsu, A.
Pukhov, A. Sunahara, K.
Takahashi, M. Allen, H.
Studies of ultra-intense laser plasma
Habara, T. Iwatani, T.
interactions for fast ignition
Matusita, T. Kawasaki, T.
Komeno, O. Maekawa, S.
Matsuo, T. Shozaki, Ka Suzuki,
H. Yoshida, T. Yamanaka, Y.
Sentoku, F. Webeer, T.W.
Barbee,Jr., and L. DaSilva

Physics of Plasmas

7 (2000) 2014-2022

2000-FP5-18

2000

K. Wakabayashi, S. Hattori, T.
Tange, Y. Fujimoto, M.
Yoshida, N. Kozu, K.A. Tanaka, Laser-induced shock compression of
N. Ozaki, Y. Sasatani, H.
tantalum to 1.7 Tpa
Takenaka, K.G. Nakamura andK. KodoJpn.J.Appl.Phys.

39 (2000) 1815-1816

2000-FP5-18

2000

T. Miyakoshi, K.A. Tanaka, R.
Kodama, K. Mima, T.
Yamanaka, Y. Kitagawa, H.
Fujita, N. Miyanaga, T.
Norimatsu, T. Kawasaki, N.
Study of ultra-intense laser propagation
Izumi, J. Sunahara, Y. Sentoku,
with measurement of back-scattered light
K. Tahakashi, H. Habara, M.
image and spectrum
Mori, T. Matsushita, T.
Sonomoto, H. Setoguchi, T.
Koase, T. Iwatani, Y. Tohyama,
M. Tanpo, PWM group, Gogroup, Mt group and T group

SPIE

3886 (2000) 505-512

2000-FP5-18

7

2000

K. Takahashi, R. Kodama, K.A.
Tanaka, H. Hashimoto, Y.
Laser-Hole Boring into Overdense Plasmas
Kato, K. Mima, F.A. Weber,
Measured with Soft X-Ray Laser Probing
T.W. Barbee,Jr, and L.B. Da
Silva

Phys.Rev.Lett.

84 (2000) 2405-2408

2000-FP5-18

8

2000

K. Mima, K.A. Tanaka and R.
KodamaExperimental research on Fast Ignitor

Inertial Fusion Sciences andApplication, edited by C.
Labaune,W J. Hogan, K.A. Tanaka(2000) 381-391

2000-FP5-18

2000

K.A. Tanaka, M. Hara, N.
Ozaki, Y. Sasatani, S.I.
Anisimov, K. Kondo, M.
Nakano, K. Nishihara, H.
Takenaka, M. Yoshida and K.
Mima

Multi-layered flyer accelerated by laser
induced shock waves

Phys. of Plasmas

7 (2000) 676-681

2000-FP5-18

2000

R. Kodama, K.A. Tanaka, Y.
Sentoku, T. Matsushita, K.
Takahashi, H. Fujita, Y.
Kitagawa, Y. Kato, T.
Yamanaka, and K. Mima

Long-Scale Jet Formation with Specularly
Reflected Light in Ultraintense Laser-Plasma Phys.Rev.Lett.
Interactions

84 (2000) 674-677

2000-FP5-18

2000

K.A. Tanaka, R. Kodama, N.
Izumi, K.Tahakashi, M. Heya,
H. Fujita, Y. Kato, Y. Kitagawa,K. Mima, N. Miyanaga, T.
Norimatsu, Y. Sentoku, A.
Self-focusing and its related interactions at
Sunahara, H. Takabe, T.
very high laser intensities for fast ignition at C.R.Acad.Sci.Paris,t.1,Serie IV
Yamanaka, T. Koase, T.I
Osaka University
watani, F. Ohtani, T.
Miyakoshi, H. Habara, M.
Tanpo, S. Tohyama, F.A.
Weber, T.W. Barbee Jr. , andL.B. Dasilva

2000 (2000) 737-744

2000-FP5-18

3

4

5

6

9

10

11

A−31

2001

Y. Kitagawa, Y. Sentoku, S.
Akamatsu, M. Mori, Y.
Tohyama, R. Kodama, K. A.
Tanaka, H. Fujita, H. Yoshida, Progress of fast ignitor studies and Petawatt
Physics of Plasmas
S. Matsuo, T. Jitsuno, T.
laser construction at Osaka University
Kawasaki, S. Sakabe, H.
Nishimura, Y. Izawa, K. Mima,and T. Yamanaka

9-5 (2001) 2202-2207

2002-FP5-30

2001

T. Kadono, M. Yoshida, N. K.
Mitani, T. Matsumura, E.
Takahashi, I. Matsushima, Y. Flyer acceleration experiments using a KrF
Owadano, Y. Sasatani, K.
laser system with a long pulse duration andLaser and Particle Beams
Fujita, N.Ozaki, K. Takamatsu, pressure and thickness of isobaric zone
M.Nakano, K. A. Tanaka, H.
induced in impacted materials
Takenaka, H. Ito, and K.
Kondo

19 (2001) 623-630

2002-FP5-30

2001

Yoshihiro Murakami,
Yoneyoshi Kitagawa, Yasuhiko Observation of proton rear emission and
Sentoku, Michiaki Mori,
possible gigagauss scale magnetic fileds
Ryosuke Kodama, Kazuo A.
from ultra-intense laser illuminated plastic
Tanaka, Kunioki Mima,andtargetTatsuhiko Yamanaka

8-9 (2001) 4138-4143

2002-FP5-30

15

2001

R. Kodama, P.A. Norreys, K.
Mima, A. Evans, R.G. Evans,
H. Fujita, Y. Kitagawa, K.
Krushelnick, T. Miyakoshi, N.
Fast heating of ultrahigh-density plasma as a
Miyanaga, T. Norimatsu, S.J.
Naturestep towards laser fusion ignition
Rose, T. Shozaki, K. Shigemori,A. Sunahara, M. Tanpo, K.A.
Tanaka, Y. Tohyama, T.
Yamanaka and M. Zepf

412 (2001) 798-802

2002-FP5-30

16

2001

Il Woo Choi, H. Daido, N.
Prepulse Effect for Recombining Plasma
Sakaya, Y. Tohyama, N. Izumi,
Produced by Ultrashort High-Intensity
R. Kodama, Y. Kitagawa,
LasersK.A.Tanaka and K. Mima

Jpn.J.Appl.Phys.

40 (2001) 1443-1447

2002-FP5-30

2001

N. Ozaki,Y. Sasatani, K.
Kishida, M. Nakano, M.
Miyanaga, K. Nagai, K.
Nishihara, T. Norimatsu, K.A. Planar shock wave generated by uniform
Tanaka, Y. Fujimoto, K.
irradiation from two overlapped partially
Wakabayashi, S. Hattori, T.
coherent laser beams
Tange, K. Kondo, M. Yoshida,
N. Kozu, M. Ishiguchi, H.
Takenaka

J. Appl. Phys.

89 (2001) 2571-2575

2002-FP5-30

2001

R. Kodama, K. Mima, K. A.
Tanaka, Y. Kitagawa, H. Fujita,
K. Takahashi, A. Sunahara, K.
Fujita, H. Habara, T. Jitsuno, Y.
Fast Ignitor research at the Institute of Laser
Sentoku, T. Matsushita, T.
Physics of Plasmas
Engineering, Osaka University
Miyakoshi, N. Miyanaga, T.
Norimatsu, H. Setoguchi, T.
Sonomoto, M. Tanpo, Y.
Toyama, and T. Yamanaka

8-5 (2001) 2268-2274

2002-FP5-30

2001

J. Sasaki, T. Nakamura, Y.
Uchida, T. Someya, K.
Shimizu, M. Shitamura, T.
Teramoto, A. B. Blagoev andS. Kawata

Beam Non-Uniformity Smoothing Using
Density Valley Formed by Heavy Ion Beam
Deposition in Inertial Confinement Fusion
Fuel Pellet

Jpn. J. Appl. Phys.

40 (2001) 968-971

2000-FP5-1

20

2001

M. Ogawa, Y. Oguri, U.
Neuner, K. Nishigori, A.
Sakumi, K. Shibata, J.
Kobayashi, M. Kojima, M.
Yoshida and J. Hasegawa

Laser Heated dE/dX Experiments in Japan

Nucl. Instrum. Methods Phys.
Res., Sect. A

464 (2001) 72-79

2000-FP5-1

21

2001

K. Shibata, A. Sakumi, R. Sato,
K. Tsubuku, T. Nishimoto, J.
Experimental Investigation of the Coulomb
Hasegawa, M. Ogawa and Y. Logarithm in Beam-Plasma Interaction
Oguri

Nucl. Instrum. Methods Phys.
Res., Sect. A

464 (2001) 225-230

2000-FP5-1

12

13

14

17

18

19

Physics of Plasmas

A−32

2001

A. Sakumi, K. Shibata, R. Sato,
Energy Dependence of the Stopping PowerK. Tsubuku, T. Nishimoto, J.
of MeV 16O Ions in a Laser-Produced
Hasegawa, M. Ogawa, Y.
PlasmaOguri and T. Katayama

Nucl. Instrum. Methods Phys.
Res., Sect. A

464 (2001) 231-236

2000-FP5-1

2001

M. Kojima, K. Nishigori, M.
Yoshida, A. Sakumi, J.
Hasegawa, U. Funk, U.
Neuner, Y. Oguri and M.
Ogawa

Nucl. Instrum. Methods Phys.
Res., Sect. A

464 (2001) 262-266

2000-FP5-1

24

2001

J. Hasegawa, Y. Nakajima, K.
Sakai, M. Yoshida, S. Fukuda,
K. NIshigori, M. Kojima, Y.
Energy Loss of 6MeV/u Iron Ions in Partially Nucl. Instrum. Methods Phys.
Oguri, M. Nakajima, K.
Ionized Helium PlasmaRes., Sect. A
Horioka, M. Ogawa, U.
Neuner and T. Murakami

464 (2001) 440-444

2000-FP5-1

25

2001

M. Yoshida, J. Hasegawa, Y.
Oguri, M. Ogawa, M.
Nakajima, K. Horioka and M.
Shiho

464 (2001) 582-586

2000-FP5-1

2001

M. Ogawa, Y. Oguri, J.
Hasegawa, T. Aoki, U. Neuner,
A. Sakumi, K. Nishigori, K.
Stopping Power of Heavy Ions in Hot Dense
Acta Physica Polonica B
Shibata, M. Kojima, M.
PlasmasYoshida, Y. Nakajima, M.
Nakajima and K. Horioka

32 (2001) 945-956

2000-FP5-1

2002

R.Kodama,K.A.Tanaka,S.Fujiok
a,H.Fujita,H.Habara,Y.Izawa,T.
Jitsuno,Y.Kitagawa,K.Krusheln
Fast heating of super-solid density plasmas
ick,K.Mima,N.Miyanaga,K.Nag
towards laser fusion ignition
ai,P.Norreys,T.Norimatsu,K.Sh
igemori,H,Shiraga,Y.Toyama,
M.Zepf and T.Yamanaka

44 (2002) B109-B119

2002-FP5-30

2002

H. Shiraga, K. Shigemori, Y.
Toyama, S. Fujioka, H. Azechi,
H. Fujita, H.Habara, T. Hall, Y.
Izawa, T. Jitsuno, Y. Kitagawa,K. M. Krushelnics, K. L.
Lancaster, K. Mima, K. Nagai, Fast heating scalable to laser fusion ignition Nature
M. Nakai, H. Nishimura,
T.Norimatsu, P. A. Norreys,
S.Sakabe, K. A. Tanaka, A.
Youssef, M. Zepf, T.
Yamanaka

418 (2002) 933-934

2002-FP5-30

29

2002

Keiji Nagai, Takayoshi
Norimatsu, Tatsuhiko
Yamanaka, Tsutomu Nishibe,Single Molecular Membrane Glue Technique
Norimasa Ozaki, Kikuo
Jpn. J. Appl. Phys.
for Laser Driven Shock Experiments
Takamatsu, Takatoshi Ono,
Motohiro Nakano, and Kazuo
A. Tanaka

41 (2002) L1184-L1186

2002-FP5-30

30

2002

T. Miyakoshi, M. S. Jovanovic,
Stimulated Raman back-scattering from aY. Kitagawa, R. Kodama, K.
mm-scale inhomogeneous plasma irradiated Physics of Plasmas
Mima, A. A. Offenberger, K.
with ultra-intense laser pulse
A. Tanaka, and T. Yamanaka

9-8 (2002) 3552-3557

2002-FP5-30

31

2002

Jian Zheng, K. A. Tanaka, T.
Miyakoshi, Y. Kitagawa, R.
Kodama, T.Kurahashi, and T.
YamanakaSpectrum of transition radiation from hot
electrons generated in ultra-intense laser
plasma interaction

Physics of Plasmas

9-8 (2002) 3610-3616

2002-FP5-30

2002

Jian Zheng, K. A. Tanaka, Y.
Harmonic emission with cyclotron satellite
Sentoku, A. A. Offenberger, Y.
structure due to strong magnetic fields
Kitagawa, R. Kodama, T.
produced by ultra-intense laser-plasma
Kurahashi, K. Mima, and T.
interaction
Yamanaka

Physics of Plasmas

9-8 (2002) 3193-3196

2002-FP5-30

22

23

26

27

28

32

Laser Plasma Induced from Solid Hydrogenfor Beam-Plasma Interaction

A simple Time-Resolved Emittance
Measurement of a Laser Ion Source with aDigital Camera

Nucl. Instrum. Methods Phys.
Res., Sect. A

Plasma Physics And Controlled
Fusion

A−33

33

2002

N. Izumi, Y. Sentoku, H.
Habara, K. Takahashi, F.
Ohtani, T. Sonomoto, R.
Kodama, T. Norimatsu, H.
Fujita, Y. Kitagawa, K. Mima,
K. A. Tanaka, and T.
Yamanaka

34

2002

35

2002

36

Observation of neutron spectrum producedby fast deuterons via ultraintense laser
Physical Review E
plasma interactions

65 (2002) 036413-1-036413-10

2002-FP5-30

Behaviour of ion temperature in electron
S. Morita, M. Goto, S. Kubo et
and ion heating regimes observed with ECH, Nuclear Fusional.
NBI and ICRF discharges of LHD

42 (2002) 1179–1183

2002-FP5-10

S. Morita, Y. Shirai, M. Goto
et al.

Observation of ablation and acceleration of
impurity pellets in the presence of energetic Nuclear Fusionions in the CHS heliotron/torsatron

42 (2002) 876–880

2002-FP5-10

2002

T. Norimatsu, K. Nagai, T.
Yamanaka, T. Endo, H.
Yoshida, Y. Sakagami

Activities on target fabrication and injection
Fusion Eng. Desig.
toward laser fusion energy in Japan

63 (2002) 587-596

2001-FP5-37

37

2002

I. Golovkin, R. Mancini, S.
Louis, Y. Ochi, K. Fujita, et al.

Spectroscopic Determination of Dynamic
Plasma Gradients in Implosion Cores

Physical Review Letters

88 (2002) 0450021-0450024

2000-ML-1

38

2002

Y. Ochi, I. Golovkin, R. C.
Mancini, M. Fukao, A.
Sunahara, et al.

Diagnostics of Electron Temperature andDensity Gradients in Laser Imploded Core
PlasmasInertial Fusion Science andApplication 2001

136-139

2000-ML-1

39

2002

K. Shibata, K. Tsubuku, T.
Experimental Study on the Feasibility of Hot
Nishimoto, J. Hasegawa, M. Plasmas as Stripping Media for MeV Heavy J. Appl. Phys.
Ogawa, Y.Oguri and A. Sakumi Ions

91 (2002) 4833-4839

2001-FP5-19

40

2002

M. Kojima, M. Mitomo, T.
Sasaki, J. Hasegawa and M.
Ogawa

Charge-State Distribution and Energy Loss of
3.2-MeV Oxygen Ions in Laser Plasma
Laser Part. Beams
Produced from Solid Hydrogen

20 (2002) 475-478

2001-FP5-19

41

2002

T. Kikuchi, M. Nakajima and K. Bunching Dynamics and Transport Window
Laser Part. Beams
Horiokaof Intense Ion Beams in Final Beam Buncher

20 (2002) 589-593

2001-FP5-19

42

2002

K. Horioka, M. Nakajima, M.
Repetitive Induction Voltage Modulator for
Watanabe, E. Hotta, M. Shiho,
Laser Part. Beams
Heavy Ion Fusion
M. Ogawa and J. Hasegawa

20 (2002) 609-612

2001-FP5-19

43

2002

K. Takayama, J. Kishiro,
Makoto Sakuda, Y. Shimosaki Superbunch Hadron Colliders
and M. Wake

Phys. Rev. Lett.

88 (2002) 144801-1-4

2001-FP5-19

44

2002

A Concept of Quasi-Equilibrium,
T. Kikuchi, M. Nakajima and K.
Recirculating Bunch Compressor for Heavy
Horioka
Ion Fusion

J. Plasma Fusion Res. Seires

20 (2002) 589-593

2001-FP5-19

45

2002

T. Kikuchi, M. Nakajima and K. A Quasi-Equilibrium Beam Compression in a
Phys. Plasmas
Horioka
Recirculator for Heavy Ion Inertial Fusion

9 (2002) 3476-3482

2001-FP5-19

46

2002

Effect of Opacity on Neon-like Argon, and
M. Masnavi, M. Nakajima and Krypton Line Intensity Ratios in Static, andK. Horioka
Cylindrically Imploding High-Density
PlasmasJpn. J. Appl. Phys.

41 (2002) 5392-5398

2001-FP5-19

47

2002

M. Watanabe, M. Nakajima,
M. Shiho, K. Takayama, J.
Kishiro and K. Horioka

Magnetic Core Characteristics for High RepRev. Sci. Instrum.
rate Induction Modulator

73 (2002) 1756-1760

2001-FP5-19

48

2002

T.Zh. Esirkepov, S.V. Bulanov,
K. Nishihara, T. Tajima, F.
Proposed Double-Layer Target for thePegorano, V.S. Khoroshkov, K.
Generation of High-Quality LaserMima, H.Daido, Y.Kato, Y.
Accelerated Ion Beams
Kitagawa, K. Nagai, and S.
SakabePhys. Rev. Lett.

89 (2002) 175003-1-4

2002-FP5-11

49

2003

Jian Zheng, K. A. Tanaka, T.
Theoretical study of transition radiation
Miyakoshi, Y. Kitagawa, R.
from hot electrons generated in the laserKodama, T. kurahashi, and T.
solid interaction
Yamanaka

Physics of Plasmas

10- (2003) 2994

2003-FP5-32

50

2003

H. Habara,R. Kodama, Y.
Sentoku, N. Izumi, Y.
Kitagawa, K. A. Tanaka,K.
Mima,and T. Yamanaka

Momentum distribution of accelerated ionsin ultra-intense laser–plasma, interactions Physics of Plasmas
via neutron spectroscopy

10- (2003) 3712

2003-FP5-32

A−34

51

2003

N. Ozaki, K. A. Tanaka, Y.
Sasatani, K. Fujita, K.
Takamatsu, and M. Nakan, M. Hugoniot measurements for polyimide with
Physics of Plasmas
Yoshida, K. Okada, E.
laser and explosives
Takahashi, and Y. Owadano,
H. Takenaka, and K. Kondo

52

2003

R.B.Stephens, S.P.Hatchett, R.
Implosion of Indirectly Driven ReentrantE. Turner, K.A. Tanaka, R.
Cone Shell Target
KodamaPhysical Review Letters

2003

K. Takamatsu, N. Ozaki, K. A.
Tanaka, T. Ono, K. Nagai, M. Equation-of-state measurements ofNakai, T. Watari, A. sunahara, polyimide at pressures up to 5.8 TPa using
M. Nakano, T. Kataoka, H.
low-density foam with laser-driven shock
Takenaka, M. Yoshida, K.
waves
Kondo, and T. Yamanaka

Physical Review E

2003

K. A. Tanaka, R. Kodama, K.
Mima, Y. Kitagawa, H. Fujita,
N. Miyanaga, K. Nagai, T.
Norimatsu, T. Sato, Y.
Sentoku, K. Shigemori, A.
Sunahara, T. Shozaki, M.
Tanpo, S. Tohyama, T.
Yabuuchi, J. Zheng, and T.
Yamanaka

55

2003

K. Okada, K. Wakabayashi, H.
Takenaka, H. Nagao, K.
Experimental Technique for Launching
Kondo, T. Ono, K. Takamatsu,
miniature flying plates using laser pulses
N. Ozaki, K. Nagai, M. Nakai,
K. A. Tanaka, and M. Yoshida

56

2003

H.Nishimura, T.Kawamura,
R.Matsui et al.

Ka spectroscopy to study energy transport
in ultrahigh-intensity laser produced
plasmasJournal of Quantitative
Spectroscopy & Radiative Transfer

57

2003

H. Yoneda, H. Morikami, K.
Ueda et al.

Ultrashort-Pulse Laser Ellipsometric PumpProbe Experiments on Gold Targets

Physical Review Letters

58

2003

T. Norimatsu, K. Nagai, T.
Takeda, K. Mima, and T.
Yamanaka

Update for the drag force on an injectedpellet and target fabrication for Inertial
fusion59

2003

Y. Ochi, I. Golovkin, R.C.
Mancini, I. Uschmann, A.
Sunahara, et al.

Temporal evolution of temperature anddensity profiles of a laser compressed core

60

2003

T. Nakamura and S. Kawata

Origin of Protons Accelerated by an Intense
Laser and the Dependence of Their Energy Phys. Rev. E
on the Plasma Density

61

2003

T. Someya, S. Kawata, T.
Nakamura, A.I. Ogoyski, K.
Shimizu and J. Sasaki

Beam Final Transport and Direct-Drive Pellet
Fusion Sci. Technol.
Implosion in Heavy-Ion Fusion

62

2003

A.I. Ogoyski, T. Someya, S.
Kawata and T. Sasaki

63

2003

64

10-6 (2003) 2475

2003-FP5-32

91-18 (2003) 185001-1-185001-4

2003-FP5-32

67 (2003) 056406-1-5

2003-FP5-32

10-5, Part2, (2003) 1925-1930

2003-FP5-32

29 (2003) 497

2003-FP5-32

81 (2003) 327–337

2003-FP5-9

91 (2003) 075004-1 - 075004-4

2003-FP5-9

Fusion Sci. Technol.

43 (2003) 339-345

2001-FP5-37

Review of Scientific Instruments

74 (2003) 237-246

2000-ML-1

67 (2003) 026403-1-10

2001-FP5-19

43 (2003) 282-289

2001-FP5-19

Heavy Ion Beam Irradiation Non-Uniformity
Phys. Lett. A
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315/5 (2003) 372-377

2001-FP5-19

T. Someya, Aleksandar
Ogoyski, S. Kawata and T.
SasakiHeavy Ion Beam Illumination Uniformity in
IEEJ Trans. FM
Heavy Ion Beam Inertial Confinement Fusion

124 (2003) 85-90

2001-FP5-19

2003

Q. Kong, S. Miyazaki, S.
Kawata, K. Miyauchi, K.
Nakajima, S. Masuda, N.
Miyanaga and Y.K. Ho

Electron Bunch Acceleration and Trappingby the Ponderomotive Force of an Intense
Short-Pulse Laser

10 (2003) 4605-4608

2001-FP5-19

65

2003

S. Miyazaki, Q. Kong, S.
Kawata and J. Limpouch

Micro Electron Bunch Generation by Intense
J. Phys. D: Appl. Phys.
Short Pulse Laser

36 (2003) 2878-2882

2001-FP5-19

66

2003

J. Hasegawa, N. Yokota, Y.
Kobayashi, M. Yoshida, M.
Kojima, T. Sasaki, H. Fukuda,
M. Ogawa and Y. Oguri

Stopping Power of Dense Helium Plasma for
Laser Part. Beams
Fast Heavy Ions

21 (2003) 7-11

2001-FP5-19

67

2003

S. Kawata, T. Someya, T.
Nakamura, S. Miyazaki, K.
Shimizu and A. Ogoyski

Heavy Ion Beam Final Transport Through an
Laser Part. Beams
Insulator Guide in HIF

21 (2003) 27-32

2001-FP5-19

53

54

Basic and Integrated studies for fast ignition Physics of Plasmas

Int. Jour. Impact Eng.

Phys. Plasmas

A−35

68

2003

J.-L. Vay, S. Kawata ,T.
Nakamura, J. Sasaki, T.
Someya and C. Deutsch

Conducting versus Insulating Walls in a
Heavy Ion Reaction Chamber

Laser Part. Beams

21 (2003) 41-46

2001-FP5-19

69

2003

M. Ogawa, M. Yoshida, M.
Nakajima, J. Hasegawa, S.
Fukata, K. Horioka and Y.
Oguri

High-Current Laser Ion Source Based on a
Low-Power Laser

Laser Part. Beams

21 (2003) 633-638

2001-FP5-19

70

2003

M. Yoshida, J. Hasegawa, J. W.
Grid-Controlled Extraction of Low-Charged
Kwan, Y. Oguri, M. Nakajima,Ions from a Laser Ion Source
K. Horioka and M. Ogawa

Jpn. J. Appl. Phys.

42 (2003) 5367-5371

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72

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T. Kikuchi, M. Nakajima and K. Beam Dynamics Simulation in Final Beam
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R. Kodama, Y.Sentoku, Z.
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432 (2004) 1005-1008

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2004

Kazuo A. Tanaka, Toshinori
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Calibration of imaging plate for high energy
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Review of Scientific Instruments
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76 (2004) 013507.1-5

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2004

R. Kodama, H. Azechi, H.
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Fast Plasma Heating in a Cone-Attached
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Nuclear Fusion

44 (2004) S276-S283

2004-FP5-11

2004

Kazuo A Tanaka, R Kodama, Y
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Plasma Phys. Control. Fusion

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2004

K. Adumi, K. A. Tanaka, T.
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Physical review Letters

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M. Koenig, T. Vinci, A.
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Equation-of-State Measurements by LaserONO Takatoshi, TANAKA
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OZAKI Norimasa, TANAKA
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ONO Takatoshi, TANAKA
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P. A. Norreys, K. L. Lancaster,C. D. Murphy, H. Habara, S.
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Jian Zheng, K. A. Tanaka, T.
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H. Habara, R. Kodama, Y.
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Physical Review E

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K. Sueda, G. Miyaji, N.
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Optics Express

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S. Sakabe, S. Shimizu, M.
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J. A. Koch, S. W. Haana, R. C.
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T. E. Cowan, J. Fuchs, H. Ruh
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Y. Sentoku, K. Mima, H. Ruhl,
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Toshi hi ro Taguchi and T
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H. Shiraga, S. Fujioka, P. A.
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Code OK2 –A Simulation Code of Ion
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Y. Shimosaki, E. Nakamura, K.
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Phys. Rev. ST-AB

7 (2004) 014201-1-8

2004-FP5-17

Resonant Heat i ng of a Cluster Plasma by
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Micro Electron Bunch Acceleration andTrapping by Intense Short Laser Pulse in
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T. Kikuchi, M. Nakajima, K.
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2004

Yoneyoshi Kitagawa, Yasuhiko
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N. Ozaki, T. Ono, K.
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J Zhang, Y T Li, Z M Sheng, Y Y
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Plasma Physics and Controlled
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H Nishimura, Y Inubushi, M
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R. B. Campbell, R. Kodama, T. Simulation of Heating-Compressed FastA. Mehlhorn, K. A. Tanaka
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121

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J. A. King, K. Akli, B. Zhang etal.

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Fuyumi ITO, Keiji NAGAI,
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K.Kasuya, Y.Kinoshita,First Wall Ablations with High-Flux Pulsed
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T. Norimatsu, D. Harding, R.
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M. Adachi, M. Miura, S. Kato,
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S. Miyazaki, K. Miyauchi, K.
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Zheng Jian, Li Zhi-Chao, Zhang Effect of sheath potential on
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Toshinori Yabuuchi, Yasuhiko
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K. Horioka, T. Kawamaru, M.
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K. Katagiri, S. Nishinomiya, T.
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112 (2008) 042086 (4pp)

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216

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T Tanimoto, A L Lei, T
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217

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A Lei, W Yu, Y Tian, H Xu, X
Effect of focus position on a high intensity
Wang, X Yang, V K Senecha, K
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112 (2008) 022089 (4pp)

2008-FP6-7

2008

H. Nakamura, Y. Sentoku, T.
Matsuoka, K. Kondo, M.
Nakatsutsumi, T. Norimatsu,
H. Shiraga, K.A. Tanaka, T.
Yabuuchi and R. Kodama

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219

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J. S. Green, V. M.
Ovchinnikov, R. G. Evans, K.
Effect of Laser Intensity on Fast-ElectronU. Akli, H. Azechi, F. N. Beg, C.
Beam Divergence in Solid-Density Plasmas
Bellei, R. R. Freeman, H.
Habara, et al.

Physical Review Letters

100 (2008) 015003

2008-FP6-7

220

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N. Nakanii, K. Kondo, Y.
Kuramitsu et al.

Applied Physics Letters

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Physical Review Letters
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Spectrum modulation of relativistic
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Optics Lettersdifferences

2008

M. C. Rushford, J. A. Britten,
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A. G. MacPhee, K. U. Akli, F.
N. Beg, C. D. Chen, H. Chen, R.
Clarke, D. S. Hey, R. R.
Freeman, A. J. Kemp, M. H.
Key, J. A. King, S. Le Pape, A.
Link, T. Y. Ma, H. Nakamura,
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D. T. Offermann, V. M.
Ovchinnikov, P. K. Patel, T. W.
Phillips, R. B. Stephens, R.
Town, Y. Y. Tsui, M. S. Wei, L.
D. Van Woerkom, and A. J.
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Review of Scientific Instruments

2008

O. Matsumoto, T. Kurita, R.
Yasuhara, T. Sekina, T.
Ikegawa, T. Kawashima, J.
Kawanaka, N. Miyanaga, T.
Norimatsu, Y. Izawa, M.
Nakatsuka, M. Miyamoto, H.
Kan, and T. Kanabe

Analysis of Parasitic Oscillation and
Evaluation of Amplifier Module of Zig-zag
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Jpn. J. Appl. Phys

47-7 (2008) 5441-5449

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O. Matsumoto, T. Kanabe, R.
Yasuhara, T. Kurita, T. Sekine,
T. Kawashima, T. Norimatsu, Analysis and Evaluation of Laser-Induced
Y. Izawa, M. Nakatsuka, M.
Damage of Zig-zag Slab Laser Amplifier
Miyamoto, H. Kan, H.
Furukawa, and S. Motokoshi

Jpn. J. Appl. Phys

47-6 (2008) 4531-4539

2005-FP5-27

2008

Y. Izawa, N. Miyanaga, J.
Kawanaka, K. Yamakawa

High Power Lasers and Their New
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J. Opt. Soc. Korea

12-3 (2008) 178-185

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226

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Ryo Yasuhara, Toshiyuki
Kawashima, Takashi Sekine,
Takashi Kurita, Tadashi
Ikegawa, Osamu Matsumoto,
Masahiro Miyamoto,Hirofumi Kan, Hidetsugu
Yoshida, Junji Kawanaka,
Masahiro Nakatsuka, Noriaki
Miyanaga, Yasukazu Izawa,and Tadashi Kanabe

213W average power of 2.4 GW pulsed
thermally controlled Nd:glass zigzag slab
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D. R. Farley, K. Shigemori, M. Non-Dimensional Scaling of Impact Fast
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S. Kawata, K. Miyazawa, A.I.
Ogoyskii, T. Kikuchi, Y.
Akasaka and Y. Iizuka

Direct-Indirect Hybrid Mode Implosion in
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112 (2008) 032028-1-4

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229

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T. Sasaki, Y. Yano, M.
Nakajima, T. Kawamura andK. Horioka

A Comparative Study of Equation of State
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Using Pulsed-Power Wire Discharges in
Water

J. Phys. Conf. Ser.

112 (2008) 042026-1-4

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T. Sasaki, T. Kikuchi, M.
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Tamped Target for Warm Dense Matter
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112 (2008) 042027-1-4

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231

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K. Kondo, M. Nakajima, K.
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Relaxation Layer in Electro-Magnetically
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J. Phys. Conf. Ser.

112 (2008) 042028-1-3

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232

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S. Kawata, M. Nakamura, Q.
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Collimated Ion Beam by a Tailored Target
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S.Kawata, M.Nakamura,
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Collimated Ion Beam by a Laser-IlluminatedIEEE Trans. Plasma Sci.
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Y. Nodera, S. Kawata, N.
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K. Katagiri, J. Hasegawa, S.
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S. Nishinomiya, K. Katagiri, T.
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J. Hasegawa, M. Ogawa and Y.
a Surface-Barrier Charged-Particle DetectorOguri

50 (2008) 606-610

2007-FP6-3

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T. Sasaki, Y. Yano, M.
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Evaluation of Copper Conductivity in Warm
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50 (2008) 611-615

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M. H. Key et al.

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15 (2008) 022701

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Y. Ueno, G. Soumagne, A.
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Reduction of debris of a CO2 laser-produced
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92 (2008) 211503

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240

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A.L.Lei et al.

Study of ultraintense laser propagation in
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Physics of Plasmas

16 (2009) 056307

2008-FP6-7

2009

Y. Mori, Y. Sentoku, K. Kondo,
K. Tsuji, N. Nakanii, S.
Fukumochi, M.Kashihara, K.
Kimura, K. Takeda, K. A.
Autoinjection of electrons into a wake field
Tanaka, T. Norimatsu,
Physics of Plasmas
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Tsuyoshi Tanimoto, H.
Nakamura, M. Tampo, R.
Kodama, E. Miura, K. Mima,and Y. Kitagawa

16 (2009) 123103

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242

2009

T. Yabuuchi, A. Das, G. R.
Kumar, H. Habara, P. K. Kaw,
R. Kodama, K. Mima, P. A.
Norreys, S. Sengupta, and K.
A. Tanaka

Evidence of anomalous resistivity for hot
electron propagation through a dense
fusion core in fast ignition experiments

New Journal of Physics

11 (2009) 093031 (9pp䠅

2008-FP6-7

243

2009

Kazuo A. Tanaka

Summary of inertial fusion sessions

Nuclear Fusion

49 (2009) 104004 (8pp)

2008-FP6-7

244

2009

Tsuyoshi Tanimoto, H.
Habara, R. Kodama, M.
Nakatsutsumi, Kazuo A.
Tanaka, K. L. Lancaster, J. S.
Green, R. H. H. Scott, M.
Sherlock, Peter A. Norreys, R.
Measurements of fast electron scaling
G. Evans, M. G. Haines, S. Kar,
generated by petawatt laser systems
M. Zepf, J. King, T. Ma, M. S.
Wei, T. Yabuuchi, F. N. Beg,
M. H. Key, P. Nilson, R. B.
Stephens, H. Azechi, K. Nagai,
T. Norimatsu, K. Takeda, J.
Valente, and J. R. Davies

Physics of Plasmas

16 (2009) 062703

2008-FP6-7

245

2009

Y. Mori, Y. Sentoku, K. Kondo Autoinjection of electrons into a wake field
et al.
using a capillary with attached cone

Physics of Plasmas

16 ( 2009) 123103-1 -123103-6

2005-FP5-9

2009

K. L. Lancaster, M. Sherlock, J.
S. Green, C. D. Gregory, P.
Hakel, K. U. Akli, F. N. Beg, S.
N. Chen,,R. R. Freeman, H.
Habara, R. Heathcote, D. S.
Hey, K. Highbarger, M. H. Key,
Effect of reentrant cone geometry on
R. Kodama,,K. Krushelnick, H.
energy transport in intense laser-plasma
Nakamura, M. Nakatsutsumi,
interactions
J. Pasley, R. B. Stephens, M.
Storm, M. Tampo, W.
Theobald, L. Van Woerkom, R.
L. Weber, M. S. Wei, N. C.
Woolsey, T. Yabuuchi, and P.
A. Norreys

Physical Review E

80 (2009) 045401

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2009

S. A. Reed, T. Matsuoka, S.
Bulanov, M. Tampo, V.
Chvykov, G. Kalintchenko, P.
Relativistic plasma shutter for ultraintense
Rousseau, V. Yanovsky, R.
laser pulses
Kodama, D. W. Litzenberg, K.
Krushelnick, and A.
Maksimchuk

248

2009

T. Kikuchi, K. Horioka

Beam Behavior under a Non-Stationary
State in High-Current Heavy-Ion Beams

249

2009

S.M. Lund, T. Kikuchi, R.C.
Davidson

250

Applied Physics Letters

94 (2009) 201117

2006-FP5-26
2007-FP6-17

Nuclear Instruments and Methods
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A 606 (2009) 31-36

2009-FP6-4
2009-FP6-8

Generation of initial kinetic distributions for
Physical Review Special Topics simulation of long-pulse charged particle
Accelerator and Beams
beams with high space-charge intensity

12 (2009) 114801-1-50

2008-FP6-1
2009-FP6-4
2009-FP6-8

2009

Hong-bo Cai1, Kunioki
Mima1, Wei-min Zhou1,
Tomoyuki Jozaki1, Hideo
Nagatomo1, Atsushi
Sunahara1, and Rodney J.
Mason2

Enhancement of the number of high energy
electrons deposited to the compressed
Physical Review Latterspellet via double cone in fast ignition

102 (2009) 1245001

2005-FP5-10

251

2009

S.Yu. Gus’kov and M.
Murakami

Fast ignition by detonating hydrodynamicflow

J. Russian Laser Research

30 (2009) 279-295

2009-FP6-3

252

2009

T. Sasaki, T. Asai, T.
Takahashi, T. Kikuchi, M.
Nakajima, K. Horioka and K.
Takayama

Planned for High Energy Density Physics
Based on All Ion Accelerator Facility

J. Plasma Fusion Res. Seires

8 (2009) 174-178

2008-FP6-1

253

2009

Y. Iizuka, S. Kawata T. Kodera, Direct-Indirect Hybrid Implosion in Heavy
A.I. Ogoyski and T. Kikuchi
Ion Inertial Fusion

J. Plasma Fusion Res. Seires

8 (2009) 1200-1203

2008-FP6-1

254

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T. Kikuchi and K. Horioka

J. Plasma Fusion Res. Seires

8 (2009) 1230-1233

2008-FP6-1
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255

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K. Horioka, T. Kawamura, M.
Nakajima, T. Sasaki, K. Kondo,
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Nucl. Instrum. Methods Phys.
Beam-Driven High Energy Density Science in
Ogawa, S. Kawata, T. Kikuchi,Res., Sect. A
Japan
M. Murakami and K.
Takayama

606 (2009) 1-5

2008-FP6-1

256

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T. Kikuchi and K. Horioka

Beam Behavior under a Non-Stationary
State in High-Current Heavy-Ion Beams

Nucl. Instrum. Methods Phys.
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S. Kawata, Y. Iizuka, Y. Kodera, Robust Fuel Target in Heavy Ion Inertial
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606 (2009) 152-156

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T. Sasaki, T. Kikuchi, M.
Nakajima, T. Kawamura andK. Horioka

Quasi-Statically Tamped Target for Warm
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Dense Matter Experiments Based on All Ion
Res., Sect. A
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606 (2009) 161-164

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259

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Study on Target Structure for Direct-Indirect
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Nucl. Instrum. Methods Phys.
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J. Hasegawa, H. Ikagawa, S.
Beam-Plasma Interaction Experiments Using Nucl. Instrum. Methods Phys.
Nishinomiya, T. Watahiki andElectromagnetically Driven Shock Waves
Res., Sect. A
Y. Oguri

606 (2009) 205-211

2008-FP6-1

261

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K. Kondo, M. Nakajima, T.
Kawamura and K. Horioka

Atomic Process in Electro-Magnetically
Driven Shock Wave

606 (2009) 223-225

2008-FP6-1

262

2009

T. Kikuchi and K. Horioka

Static Analysis of Possible Emittance Growthof Intense Charged Particle Beams with
Phys. Plasmas
Thermal Equilibrium Distribution

16 (2009) 050703-1-4

2008-FP6-1
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263

2009

Y. Aoyama, M. Nakajima andK. Horioka

Counter-Facing Plasma Focus System as a
Repetitive and/or Long-Pulse High Energy
Density Plasma Source

Phys. Plasmas

16 (2009) 110701-1-3

2008-FP6-1

264

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S. Kawata, Y. Nodera, J.
Limpouch and O. Klimo

Efficient Production of Proton Beam in
Laser-Illuminated Tailored Microstructured
TargetIEEE Trans. Plasma Sci.

37 (2009) 481-486

2008-FP6-1

Halo Formation and Emittance Growthduring Bunch Compression of High-Current
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A. Andreev, K. Platonov and S. Ion Acceleration by Short High Intensity
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2008-FP6-1

266

2009

Takeshi Higashiguchi andNoboru Yugami

Short-pulse, high-power microwave sourcewith a laser-induced sheet plasma mirror

Journal of Applied Physics

105 (2009) 093301

2006-FP5-23

267

2009

Makoto Nakagawa, Ryosuke
Kodama, Takeshi
Higashiguchi, and Noboru
Yugami

Generation of terahertz radiation via anelectromagnetically induced transparency at
Physical Review E
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80 (2009) 025402

2006-FP5-23

2010

Hideaki Habara, Kazuhide
Ohta, and Kazuo A. Tanaka, G.
Ravindra Kumar, M.
Direct, Absolute, and In Situ Measurement
Krishnamurthy, Subhendu
of Fast Electron Transport via Cherenkov
Kahaly, Sudipta Mondal,
Emission
Manoj kumar Bhuyan, and R.
Rajeev, Jian Zheng

Physical Review Letters104 䠄2010䠅 055001

2008-FP6-7

2010

Hideaki Habara, Kazuhide
Ohta, Kazuo A. Tanaka, G.
Ravindra Kumar, M.
Krishnamurthy, Subhendu
Kahaly, Sudipta Mondal,
Manoj kumar Bhuyan, R.
Rajeev, and Jian Zheng

Phys. Plasmas

17 (2010) 056306

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Measurement of high energy density
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A−50

2.ConferencePaper
No

Year

Authors

1

2000

I. Golovkin, R. Mancini, S.
Louis, Y. Ochi, K. Fujita, et al.

2

2000

3

Title of Paper

Conference Name

Month Date, Year, Place, CountryYear-Category-No.

Topical Conference on High
Temperature Plasma Diagnostics

June 18-22, 2000, Tucson, USA

2000-ML-1

Diagnostics of imploded core plasma
Y. Ochi, K. Fujita, M. Fukao, I.
dynamics using time-resolved x-ray spectra
Niki, H. Nishimura, et al.
and x-ray monochromatic images

APS 42nd annual meeting of DPP

Oct. 23-27, 2000, Quebec, Canada

2000-ML-1

2000

I. Golovkin, R. Mancini, S.
Louis, Y. Ochi, K. Fujita, et al.

Spectroscopic determination of plasma
gradients in ICF imploded cores

Radiative Properties of Hot Dense
Matter

Oct.30-Nov.3, 1999, Santa Barbara,USA

2000-ML-1

4

2001

H.Nishimura, Y.Ochi,
T.Kawamura, K.Fujita,
I.Golovkin, R.Mancini, et al.

X-ray spectroscopic measurement of laser
imploded hot core and its extension to fast
igniter experiments

5th Fast Ignitor Workshop

Jne 18-22, 2001, Madeira, Portugal

2000-ML-1

5

2001

Diagnostics of Electron Temperature andY. Ochi, K. Fujita, M. Fukao, A.
Density Gradients in Laser Imploded Core
Sunahara, H. Nishimura, et al.
Plasmas2nd International Conference on
Inertial Fusion Sciences andApplications

Sep.10-14, 2001, Kyoto, Japan

2000-ML-1

6

2001

X-ray spectroscopic measurements ofY. Ochi, K. Fujita, M. Fukao, H.
temporal variation of ICF core plasma
Nishimura, A. Sunahara, et al.
gradients

APS 43rd annual meeting of DPP

Oct.29-Nov.2, 2001, Long Beach,USA

2000-ML-1

7

2001

T. Nakamura, M. Shitamura,Y. Uchida and S. Kawata

Constrained Interpolation Profile Scheme
for Solving the Hyper-Dimensional VlasovMaxwell System in Laser-Plasma

The 2nd International Conferenceon Inertial Fusion Sciences andApplications (IFSA2001)

Sep. 9-14, 2001, Kyoto, Japan

2000-FP5-1

8

2001

Y. Uchida, T. Nakamura, K.
Direct Numerical Solution of Collision Term
Shimizu, M. Shitamura and S. in the Fokker-Planck Equation Toward a
KawataLaser-Plasma Interaction

The 2nd International Conferenceon Inertial Fusion Sciences andApplications (IFSA2001)

Sep. 9-14, 2001, Kyoto, Japan

2000-FP5-1

9

2001

J. Hasegawa, Y. Nakajima, K.
Sakai, Y. Oguri, M. Nakajima,
K. Horioka and M. Ogawa

The 2nd International Conference
Development of High-Brightness Ion Sources
on Inertial Fusion Sciences andUsing Moderate Power Lasers
Applications (IFSA2001)

Sep. 9-14, 2001, Kyoto, Japan

2000-FP5-1

10

2001

Y. Oguri, K. Tsubuku, K.
Shibata, T. Nishimoto, J.
Hasegawa and M. Ogawa

Charge-Changing Processes of Low-Energy
Heavy Ions in a Dense Non-Hydrogenic
PlasmaThe 2nd International Conferenceon Inertial Fusion Sciences andApplications (IFSA2001)

Sep. 9-14, 2001, Kyoto, Japan

2000-FP5-1

11

2002

Y. Ochi, I. Golovkin, R.C.
Mancini, I. Uschmann, A.
Sunahara, et al.

Evolution of Temperature and Density
Profiles of a Laser Compressed Core

Topical Conference on
High-Temperature Plasma
Diagnostics

Jul. 8-11, 2002, Madison, USA

2000-ML-1

12

2003

H. Shiraga, S. Fujioka, R.
Kodama, K.A. Tanaka, R.B.
Stephens, P. Jaanimagi, C.
Stoeckl, T.C. Sangster, D. D.
Meyerhofer, S.P. Hatchett

10-ps X-Ray Imaging of Cone-Shell Target
Implosion at OMEGA laser

3rd International Conference on
Inertial Fusion Science andApplications

September 8-12, 2003, Double Tree
Hotel, Monterey, California, USA

2002-FP5-33
2003-FP5-28

13

2003

T. Kikuchi, T. Katayama, M.
Nakajima and K. Horioka

Emittance Growth and Particle Distributions
Asian Particle Accelerator
during Final Beam Bunching in Heavy Ion
Conference (APAC2004)
Fusion DriverMar. 22-26, 2004, Gyeongju, Korea

2001-FP5-19

14

2003

T. Kikuchi, S.M. Lund and T.
Katayama

Possible Parameters for Bunch Compression Asian Particle Accelerator
in a Ring in Future RIKEN Projects
Conference (APAC2004)

Mar. 22-26, 2004, Gyeongju, Korea

2001-FP5-19

15

2003

S. Kawata, Shuji Miyazaki,
Qing Kong, Koichi Miyauchi,
Jiri Limpouch and A.A.
Andreev

High Energy Particle Acceleration by HighPower Laser

The 9th Conference on Laser
Optics (LO2003)

Jun. 30-Jul. 4, 2003, St. Petersburg,
Russia2001-FP5-19

16

2004

Hiroyuki Shiraga

Multi-Imaging X-Ray Streak Camera for
Diagnosing Laser-Imploded Core Plasmas(invited)

15th Topical Conference on HighTemperature Plasma Diagnostics

April 19-22, 2004, San Diego, USA

2002-FP5-33
2003-FP5-28
2003-FP5-29

17

2004

Hiroyuki Shiraga

Dynamics of imploded shell target with cone International Workshop on Fast
for fast ignition observed with MultiIgnition and High Field Physics
Imaging X-ray Streak Camera (invited)
2004

April 25-29, 2004, Kyoto, Japan

2002-FP5-33
2003-FP5-28
2003-FP5-29

A Spectroscopy Diagnostics of Plasma
Gradients In ICF Imploded Cores

A−51

18

2004

H. Shiraga, S. Fujioka, H.
Nagatomo, R. Kodama, K.A.
Tanaka, H. Azechi, R.B.
Stephens, P. Jaanimagi, C.
Stoeckl, D. D. Meyerhofer,
S.P. Hatchett

19

2004

H. Shiraga

20

2004

K. Koyama, E. Miura, S. Kato,
Generation of Quasi-monoenergetic HighN. Saito, M. Adachi, A. Ogata,energy Electron Beam by Plasma Wave
S. Masuda, and M. Tanimoto

Eleventh Advanced Accelerator
Concepts Workshop

Jun. 21-26, 2004, Stony Brook, New
York, USA2004-FP5-28

21

2004

Ion Production Enhancement by RearYoshio Wada, Yasuo
Focusing and Prepulse in Ultrashort-Pulse
Shigemoto, and Atsushi Ogata
Laser Interaction with Foil Targets

Eleventh Advanced Accelerator
Concepts Workshop

Jun. 21-26, 2004, Stony Brook, New
York, USA2004-FP5-28

22

2004

Yoneyoshi Kitagawa, Mitsuru
Uesaka, Kazuyoshi Koyama,Kaszuhisa Nakajima, Toshiki
Tajima, Hiroyuki Daido,
Review of Advanced Accelerator Concepts R Eleventh Advanced Accelerator
Atsushi Ogata, Koshichi& D in Japan
Concepts Workshop
Nemoto, Yasushi Nishida,
Noboru Yugami, Shuji
Miyamoto, and Katsuhiro
DobashiJun. 21-26, 2004, Stony Brook, New
York, USA2004-FP5-28

23

2004

S. Kawata, T. Someya, T.
Kikuchi and A.I. Ogoyski

Final Transport and Target Illumination

The 15th International Symposium
Jun. 7-11, 2004, Princeton, NJ, USA
on Heavy ion Inertial Fusion

2004-FP5-17

24

2004

T.kikuchi, T.Someya, S.
Kawata, N. Nakajima, K.
Horioka and T. Katayama

Beam Dynamics Simulation during Final
Bunching and Transport for Heavy Ion
Inertial Fusion

International Computational
Accelerator Physics (ICAP2004)

Jun. 29-Jul. 2, 2004, St. Petersburg,
Russia2004-FP5-17

25

2005

K.Kasuya, T.Norimatsu, S.
Nakai, A.Prokopiuk andW.MrozIFE Chamber Wall Ablations with High-Flux
Pulsed Beams Including Ions and UV Laser
LightsThird Technical Meeting on
Physics and Technology of Inertial October 11-13, 2004, KAIST, Daejon,
Fusion Energy Targets andRepublic of Korea
Chambers

2005-FP5-27

26

2005

K.Kasuya, T.Notimatsu,
K.Nagai, et al.

Observation of Various Material Surfaces
Irradiated and Cratered with Focused ArF
Laser Lights

15th International Symposium on
Gas Flow and Chemical Lasers &High Power Laser Conference

30 August-3 September 2004,
Prague, Czech Republic

2005-FP5-27

27

2005

K.Kasuya, T.Notimatsu,
S.Nakai, T.J.Renk, and W.
Mroz

Eighth Japan-China Symposium on
Material Surface Ablation with Light andMaterials for Advanced Energy
Medium-Mass Pulsed Ion Beams for Future
Systems and Fission & Fusion
IFE Reactor Design
Engineering

October 4-8, 2004, Sendai, Miyagi,
Japan, 47-52 (2005)

2005-FP5-27

28

2005

H. Shiraga, H. Nagatomo, S.
Fujioka, R. Kodama, K.A.
Tanaka, R.B. Stephens, P.
Jaanimagi, C. Stoeckl

Nonuniform Core and Jet Formation inCone-Shell Implosion

4th International Conference on
Inertial Fusion Sciences andApplications

September 4-9, 2005, Biarritz,
France2002-FP5-33
2003-FP5-28
2003-FP5-29

29

2005

T. Kikuchi, T. Someya, S.
Kawata, M. Nakajima and K.
Horioka

Instability and Emittance Growth in HighCurrent Heavy Ion Beam Bunching

The 32nd IEEE International
Conference on Plasma Science
2005 (ICOPS2005)

Jun. 13-17, 2005, Monterey, CA, USA

2004-FP5-17

30

2005

T. Kikuchi, T. Someya, S.
Kawata, M. Nakajima and K.
Horioka

Emittance Growth and Instability induced by The 4th International Conference
Space Charge Effect during Final Beamon Inertial Fusion Sciences andBunching in HIF Accelerator System
Applications (IFSA2005)

Sep. 4-9, 2005, Biarritz, France

2004-FP5-17

31

2005

T. Kikuchi, T. Someya, M.
Seino, K. Miyazawa, S.
Kawata, M. Nakajima and K.
Horioka

Effect of Dipole Mode Oscillation during
The 47th Annual Meeting of theHigh-Current Heavy Ion Beam Transport and American Physical Society Division
Longitudinal Compressionof Plasma Physics

Oct. 24-28, 2005, Denver, CO, USA

2004-FP5-17

32

2005

T. Kikuchi, S. Kawata, T.
Someya, K. Horioka, M.
Nakajima and T. Katayama

Beam Dynamics and Pulse Duration Control
2005 Particle Accelerator
During Final Beam Bunching in Driver
Conference (PAC05)
System for Heavy Ion Inertial Fusion

May 16-20, 2005, Knoxville, TN, USA

2004-FP5-17

Imploded Core Plasma Dynamics of ConeShell Targets

46th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

Nov. 15-19, 2004, Savannah, GA,USA

2002-FP5-33
2003-FP5-28
2003-FP5-29

A new approaach toward time- and spaceresolved measurements of fast ignition

Japan-US Workshop on High
Irradiance Laser and Plasma
Diagnostic Technologies

Nov. 29-Dec. 1, 2004, Osaka, Japan

2002-FP5-33
2003-FP5-28
2003-FP5-29

A−52

33

2006

S. Kawata, K. Horioka, M.
Murakami, Y. Oguri, J.
Hasegawa, K. Takayama, H.
Yoneda, T. Kikuchi, T.
Kawamura and M. Ogawa

34

2006

K. Li, K. Ninomiya, T.
Higashiguchi and N. Yugami

Generation EM Waves by Laser Plasma
Interaction Experiments in Utsunomiya
University

35

2006

N. Ohata, T. Higashiguchi, H.
Kawanago, K. Yaegashi, I.
Takano, K. Li and N. Yugami

36

2007

K.Kasuya, S.Ozawa, S.Suzuki,
K.Esato, M.Akiba, W.Mroz,
Applications of Laser and Particle Beam
A.Prokopiuk, M.Sato,
Apparatuses to Fusion Reactor Plasma
K.Shimoda, T.Norimatsu,
Facing Furface Research Works
M.Nakai, K.Nagai, T.Ohshige,
H.Furukawa

37

2007

T. Kikuchi, S. Kawata and K.
Horioka

38

2007

39

Studies on Heavy Ion Fusion and HighEnergy Density Physics in JapanThe 16th International Symposium
on Heavy Ion Inertial Fusion

Jul. 9-14, 2006, Saint-Malo, France

2005-FP5-1

12th Advanced Accelerator
Concepts Workshop

July 10–15, 2006, Lake Geneva,
Wisconsin, USA

2006-FP5-23

Experiments of Frequency Upshift by Use of 12th Advanced Acceleratora Laser-Produced Ionization Front
Concepts Workshop

July 10–15, 2006, Lake Geneva,
Wisconsin, USA

2006-FP5-23

September 13, 2007, Kobe, Japan

2005-FP5-27

Particle Dynamics at Stagnation Point during
2007 Particle Accelerator
Longitudinal Bunch Compression of High
Conference (PAC07)
Current Beams

Jun. 25-29, 2007, Albuquerque, NM,USA

2006-FP5-10
2007-FP6-20

T. Kikuchi, S. Kawata and K.
Takayama

Half-Mini Beta Optics with a Bunch Rotation2007 Particle Accelerator
for Warm Dense Matter Science Facility inConference (PAC07)
KEK

Jun. 25-29, 2007, Albuquerque, NM,USA

2006-FP5-10
2007-FP6-20

2007

S. Kawata, M. Nakamura, R.
Sonobe, S. Miyazaki, N.
Onuma and T. Kikuchi

Collimated Ion Beam by a Laser-Illuminated 2007 IEEE Pulsed Power andTailored Target
Plasma Science Conference

Jun. 17-22, 2007, Albuquerque, New
Mexico, USA

2006-FP5-10

40

2007

S. Kawata, K. Miyazawa, A.I.
Ogoyskii, T. Kikuchi, Y.
Akasaka and Y. Iizuka

Direct-Indirect Hybrid Mode Implosion in
Heavy Ion Inertial Fusion

Sep. 9-14, 2007, Kobe, Japan

2006-FP5-10

41

2007

Nobuo Ohata, Kun Li, Hiroshi
High power, 1-THz source based on a
Kawanago, Kenta, Yaegashi,
femtosecond laser-pumped DC to AC
Takeshi Higashiguchi, andRadiation Converter scheme
Noboru Yugami

CLEO EUROPE

June 17-22, 2007, Munich, Germany

2006-FP5-23

42

2007

Kun Li, Tsukasa Oshima,
Masafumi Hikita, Takeshi
Higashiguchi, and Noboru
Yugami

CLEO EUROPE

June 17-22, 2007, Munich, Germany

2006-FP5-23

43

2007

Nobuo Ohata, Kenta Yaegashi,THz radiation from a DARC source via a
Kun Li, Takeshi Higashiguchi,
laser-produced relativistic ionization front
and Noboru Yugami

SPIE Optics East

Sep. 2007, Boston, USA

2006-FP5-23

44

2008

N. Ozaki (invited)

Extreme Off-Hugoniot Generated by
Reverberating Shock Compression

Mar. 15-19, 2009, Hakone, Japan

2006-FP5-26
2007-FP6-17

45

2008

S. Kawata, Y. Nodera, N.
Onuma, M. Nakamura, R.
Sonobe, T. Kikuchi, Q. Kong,
P.X. Wang, J. Limpouch, O.
Klimo and A. Andreev

The 35th IEEE International
Laser-Produced Collimated Proton Beam byConference on Plasma Sciencea Tailored Thin Foil Target(ICOPS2008)

Jun. 15-19, 2008, Karlsruhe,
Germany

2007-FP6-3

46

2008

S. Kawata, Y. Nodera, J.
Limpouch, O. Klimo and A.
Andreev

Efficient Collimated-Proton Beam
The 12th International Conference
Generation by an Intense-Laser-Illuminatedon Laser Optics
Tailored Target

Jun. 23-28, 2008, St. Petersburg,
Russia2007-FP6-3

47

2008

S. Kawata, Y. Iizuka, Y. Kodera, Robust Fuel Target in heavy ion inertial
A.I. Ogoyski and T. Kikuchi
fusionThe 17th International Symposium
on Heavy Ion Inertial Fusion(HIF2008)

Aug. 4-8, 2008, Tokyo, Japan

2007-FP6-3

2008

K. Horioka, T. Kawamura, M.
Nakajima, T. Sasaki, K. Kondo,
Activities on Heavy Ion Inertial Fusion and
The 17th International Symposium
Y. Oguri, J. Hasegawa, M.
Beam-Driven High Energy Density Science in on Heavy Ion Inertial Fusion
Ogawa, S. Kawata, T. Kikuchi,Japan(HIF2008)
M. Murakami and K.
Takayama

Aug. 4-8, 2008, Tokyo, Japan

2007-FP6-3

48

4th IAEA Technical Meeting on
Physics and Technology of IFE
Targets and Chambers

The 5th International Conferenceon Inertial Fusion Sciences andApplications (IFSA2007)

Optical guiding in gas-filled capillarydischarge plasmas waveguide for electron
acceleration application

International
Workshop on Warm Dense Matter

A−53

49

2008

H. Habara et al.

Electron acceleration in ultra-intense laser(>1018 Wcm-2) interactions with submicron structured targets

The 50th Annual meeting of
Division of Plasma Physics,
American Physical Society

Nov. 17-21, 2008, Dallas, USA

2008-FP6-5

50

2008

H. Habara et al.

The 50th Annual meeting ofStudy of ultra-intense laser propagation in
Division of Plasma Physics,
overdense plasmas for fast ignition (invited)
American Physical Society

Nov. 17-21, 2008, Dallas, USA

2008-FP6-5

51

2008

Takeshi Higashiguchi,
Plasma Parameter of a Capillary DischargeHiromitsu Terauchi, Jin-xiang Produced Plasma Channel to Guide an
Bai, and Noboru Yugami
Ultrashort Laser Pulse

13th Advanced Accelerator
Concept Workshop

July, 2008, Santa Cruz, USA

2006-FP5-23

52

2008

Masashi Kudo, Takeshi
Higashiguchi, and Noboru
Yugami13th Advanced Accelerator
Concept Workshop

July, 2008, Santa Cruz, USA

2006-FP5-23

53

2008

Takeshi Higashiguchi,
Frequency Upshift and Radiation of the THz
Hideyuki Hasegawa, Hirofumi
13th Advanced Accelerator
Electromagnetic Wave via an UltrashortNishimai, Noboru Yugami,
Concept Workshop
Laser-Produced Ionization Front
and Patric Muggli

July, 2008, Santa Cruz, USA

2006-FP5-23

54

2009

Hideaki Habara, Masashi
Yamamoto, Takahiro
Kurahashi, Kenji Kida andKazuo A. Tanaka

Development of High-Order Harmonic Light
Proceedings of the 14th
Spectrometer for Observation of Strong
International Congress on Plasma
Magnetic Field Generated by Fast Electrons
Physics (ICPP2008)
in Laser-Plasma Interactions

2009.9.8-12, Fukuoka, Japan

2008-FP6-7

55

2009

Proceedings of the 14th
A. Okabayashi, T. Yabuuchi, H. Monte-Carlo Simulations for Heating ofInternational Congress on Plasma
Habara, and K. A. Tanaka
Superdense Matter by Relativistic Electrons
Physics (ICPP2008)2009.9.8-12, Fukuoka, Japan

2008-FP6-7

56

2009

H. Nakamura, Y. Arikawa, H.
Habara, M. Isobe, R. Kodama,
M. Koga, M. Nakai, H.
Developments of nuclear diagnostics for fast The 238th ACS National Meeting &Nishimura, T. Ozaki, Y.
ignition experiments in laser fusion (invited) Exposition Fall 2009
Sakawa, N. Sarukura, H.
Shiraga, KA. Tanaka, H. Azechi

Aug. 16-20,2009, Washington DC,
USA

2006-FP5-26
2007-FP6-17

57

2009

N. Ozaki (invited)

International Conference
on High Pressure Science andTechnology (AIRAPT 2009)

July 26-31, 2009, Tokyo, Japan

2006-FP5-26
2007-FP6-17

58

2009

N. Ozaki, K. Miyanishi, T.
Sano, T. Kimura, T. Endo,
Attempts of pressure standard material's
Fumio Kawamura, A. Hirose,
isentrope
R. Kodama, E. Brambrink, A.
measurement and semiconductor/metal
Benuzzi-Mounaix, A. Diziere,
sample recovery using laser-driven ramp
H. Wei, M. Koenig, Tommaso
compression
Vinci, R. Smith, O. Sakata,
Youichi Sakawa

16th. American Physical Society
Topical Conreference on Shock
Compression on Condensed
MatterJune 28- July 3, Nashvile, USA

2006-FP5-26
2007-FP6-17

59

2009

T. Kikuchi, K. Horioka

Possible emittance growth due tononuniform particle distribution in beams
with thermal equilibrium condition

Particle Accelerator Conference
2009 (PAC09)

May 4-8, 2009, Vancouver, Canada

2009-FP6-4
2009-FP6-8

60

2009

T. Kikuchi, T. Sasaki, Nob.
Harada, A. Namprom, C.
Buttapeng, K. Horioka, K.
Takayama

Beamline for warm dense matter
Particle Accelerator Conference
experiment using the KEK digital accelerator 2009 (PAC09)

May 4-8, 2009, Vancouver, Canada

2009-FP6-4
2009- FP6-8

61

2009

M.Murakami, H.Nagatomo

Progress on impact ignition

7th Direct Drive and Fast Ignition
WorkshopNov 2-6, 20090, Washington DC,
USA

2009-FP6-3

62

2009

T. Kikuchi and K. Horioka

Possible Emittance Growth due toNonuniform Particle Distribution in Beams
with Thermal Equilibrium Condition

Particle Accelerator Conference
2009 (PAC09)

May 4-8, 2009, Vancouver, Canada

2008-FP6-1

63

2009

T. Kikuchi, T. Sasaki, Nob.
Harada, A. Namprom, C.
Buttapeng, K. Horioka and K.
Takayama

Beamline for Warm Dense Matter
Experiment Using the KEK Digital
Accelerator

Particle Accelerator Conference
2009 (PAC09)

May 4-8, 2009, Vancouver, Canada

2008-FP6-1

Compression of An Ultrashort Laser Pulse
via Self-Phase Modulation in An Argon
ChannelExtreme off-Hugoniot experimens using
high-power laser

A−54

The 7th Direct Drive and Fast
Ignition Workshop

May 3-6, 2009, Prague, Czech
Republic

2008-FP6-1

S. Kawata, Y. Nodera, K.
Takahashi, Y. Ma, Z. Sheng, O. Efficient Laser Ion acceleration in an
Klimo, J. Limpouch, Q. Kong, Intense-Short Pulse Laser Foil Interaction
A. Andreeve and P. Wang

The 8th Pacific Rim Conference on
Lasers and Electro-Optics

Aug. 31-Sep. 3, 2009, Shanghai,
China

2008-FP6-1

2009

A Beam-Driven Warm-Dense-Matter
J. Hasegawa, Y. Oguri, K.
Horioka, T. Kikuchi, T. Sasaki, Experiment Using Quasi-IsentropicallyS. Kawata and K. Takayama
Compressed Targets

The 6th International Conferenceon Inertial Fusion Sciences andApplications (IFSA2009)

Sep. 6-11, 2009, San Francisco, CA,USA

2008-FP6-1

67

2009

Noboru Yugami, Takeshi
Higashiguchi, and Ryosuke
KodamaApr. 2009, Prague, Czech Republic

2006-FP5-23

68

2009

Takeshi Higashiguchi,
Hiromitsu Terauchi, Jin-xiang Plasma diagnostics of a capillary plasmaBai, Noboru Yugami, andusing pulse power
Toyohiko Yatagai

SPIE Europe

Apr. 2009, Prague, Czech Republic

2006-FP5-23

69

2009

Takeshi Higashiguchi, Masashi
Compression of an ultrashort laser pulse via
Kudo, Noboru Yugami, andSPIE Europe
self-modulation in argon gas
Eiji J. Takahashi

Apr. 2009, Prague, Czech Republic

2006-FP5-23

64

2009

S. Kawata

65

2009

66

Efficient Laser Ion Beam Generation

Possibility of high power THz radiation via
electromagnetically induced transparency at
SPIE Europe
ion acoustic frequency region in laserproduced dense plasmas

A−55

CHAPTER4JIFT
1.JournalPaper
Vol. (Year) Page (Start) -Page(End) or
Identification No.

Year-Category-No.

W. C. Chou, R. Matsumoto, T.
Dynamics of the Parker-Jeans instability in a
Tajima, M. Umekawa, and K.
Ap. J.
galactic gaseous disk
Shibata

538 (2000) 710-727

2000-JF1-06

2000

N. Mizuguchi, T. Hayashi, and Convective loss of heat energy excited in theContributions to Plasma Physics
T. Satoedge region of spherical tokamak

40-3-4 (2000) 316-321

2000-JF1-07

3

2000

N.N. Gorelenkov, S. Bernabei,
C. Z. Cheng, K. Hill, R.
Stability properties of toroidal Alfvén modes
Nazikian, S. Kaye, Y. Kusama,
Nucl. Fusion
driven by fast particles
G. J. Kramer, K. Shinohara, T.
Ozeki, and M. V. Gorelenkova

40-7 (2000) 1311-1323

2000-JF2-05

4

2000

S. M. Mahajan and Z. Yoshida

A collisionless self-organizing model for the
Phys. Plasmas
high-confinement (H-mode) boundary layer

7-2 (2000) 635-649

2000-JF1-01

5

2000

G. Rewoldt, L.-P. Ku, W. M.
Tang, H. Sugama, N.
Drift mode calculations for the Large Helical
Nakajima, K. Y. Watanabe, S.
Phys. Plasmas
DeviceMurakami, H. Yamada, andW. A. Cooper

7 (2000) 4942-4297

2000-JF1-04

6

2000

H. Sugama

Gyrokinetic field theory

7 (2000) 466-480

2000-JF2-06

7

2000

A. Zhidkov, A. Sasaki, and T.
TajimaEmission of MeV multiple-charged ions frommetallic foils irradiated with an ultrashortPhys. Rev. E
laser pulse

61-3 (2000) R2224-R2227

2000-JF1-06

8

2000

A. Zhidkov, A. Sasaki, T.
Utsumi, I. Fukumoto, T.
Tajima, et al.

Prepulse effects on the interaction of
intense femtosecond laser pulses with high- Phys. Rev. E
Z solids

62-5 (2000) 7232-7240

2000-JF1-06

9

2000

A. Zhidkov, A. Sasaki, and T.
TajimaEnergetic multiple charged ion source on
short pulse laser irradiated foils

Rev. Sci. Instr.

71 (2000) 931-934

2000-JF1-06

10

2001

S. Ohsaki, N. Shatashvili, Z.
Yoshida and S. M. Mahajan

Magnetofluid coupling: Eruptive events in
the Solar Corona

Astrophys. J.

559 (2001) L61-L65

2000-JF1-09

11

2001

Shuichi Ohsaki, Zensho
Yoshida, Nana Shatashvili,
and Swadesh M. Mahajan

Eruptive events in the solar atmosphere

Institute for Fusion Studies

Report No. IFS-927 (2001)

2000-JF1-01

12

2001

T.-H Watanabe, H. Sugama,
and T. Sato

A nondissipative simulation method for thedrift kinetic equation

J. Phys. Soc. Jpn.

70-12 (2001) 3565-3576

2001-JF2-08

13

2001

Hantao Ji, Jeremy Goodman,
and Akira Kageyama

Magnetorotational instability in a rotating
liquid metal annulus

Mon. Not. R. Astron. Soc.

325 (2001) L1–L5

2000-JF1-11

14

2001

A. Maluckov, N. Nakajima, M. Statistical properties of the particle radial
Okamoto, S. Murakami, and diffusion in a radially bounded irregular
R. Kanno
magnetic field

National Institute for Fusion
Science

Report No. NIFS-715 (2001)

2001-JF1-10

2001

K. Shinohara, Y. Kusama, G. J.
Kramer, M. Takechi, A.
Morioka, M. Ishikawa, N.
Oyama, K. Tobita, T. Ozeki, S.
Takeji, S. Moriyama, T. Fujita,
Alfvén eigenmodes driven by Alfvénic beam
T. Oikawa, T. Suzuki, T.
Nucl. Fusionions in JT-60U
Nishitani, T. Kondoh, S. Lee,
M. Kuriyama, N. N.
Gorelenkov, R. Nazikian, G. Y.
Fu, C. Z. Cheng, and A.
Fukuyama

41 (2001) 603

2001-JF1-05

No

Year

1

2000

2

15

Authors

Title of Paper

JournalPhys. Plasmas

A−56

16

2001

K. Ichiguchi, M. Wakatani, T.
Unemura, T. Tatsuno, and B.
A. Carreras

Improved stability due to local pressure
flattening in stellarators

Nucl. Fusion

41-2 (2001) 181-187

2001-JF1-13

17

2001

B. A. Carreras, V. E. Lynch, K.
Ichiguchi, M. Wakatani, andT. Tatsuno

On the application of local asymptotic
criteria to stellarator stability

Phy. Plasmas

8-3 (2001) 990-996

2001-JF1-13

18

2001

S. M. Mahajan, R.
Miklaszewski, K. I.
Nikol'skaya, and N. L.
Shatashvili

Formation and primary heating of the solar
corona: Theory and simulation

Phys. Plasmas

8-4 (2001) 1340-1357

2000-JF1-01

19

2001

Gyrokinetic study of ion temperature
J. Q. Dong, W. Horton, and Y.
gradient instability in vicinity of flux surfaces Phys. Plasmas
Kishimotowith reversed magnetic shear

8-1 (2001) 167-173

2000-JF1-02

20

2001

H. Sugama, T.-H Watanabe,
and W. Horton

Collisionless kinetic-fluid closure and its
application to the three-mode ion
temperature gradient driven system

Phys. Plasmas

8-6 (2001) 2617-2628

2001-JF1-08

21

2001

Z. Yoshida, S. M. Mahajan, S.
Ohsaki, M. Iqbal, and N.
Shatashvili

Beltrami fields in plasmas: Highconfinement mode boundary layers andhigh beta equilibria

Phys. Plasmas

8-5 (2001) 2125-2131

2001-JF1-09

22

2001

A. G. Zhidkov, A. Sasaki, I.
Fukumoto and T. Tajima, etal.

Pulse duration effect on the distribution ofenergetic particles produced by intense
femtosecond laser pulses irradiating solids

Phys. Plasmas

8-8 (2001) 3718-3723

2001-JF2-04

23

2001

F. Volponi, Z. Yoshida, and S.
Mahajan

Asymptotic analysis and renormalized
perturbation theory of non-Hermitian
dynamics

Phys. Rev. E

64 (2001) 026312-1-6

2000-JF1-01

24

2001

Vortex solitons: Mass, energy, and angular
T. Tatsuno, V. Berezhiani, andmomentum bunching in relativistic electron- Phys. Rev. E
S. M. Mahajan
positron plasmas

63 (2001) 046403-1-7

2000-JF1-01

25

2001

Francesco Volponi, Swadesh
M. Mahajan, and Zensho
YoshidaPhys. Rev. E

64 (2001) 026312

2001-JF1-09

26

2001

T. Tajima, Y. Kishimoto, and T.
Cluster fusion
Masaki

Physica Scripta

T89 (2001) 45-48

2001-JF2-04

27

2001

A. Maluckov, N. Nakajima, M.
Statistical properties of the neoclassicalOkamoto, S. Murakami, anddiffusion in a tokamak equilibrium
R. Kanno

Plasma Phys. Control. Fusion

43 (2001) 1211-1226

2001-JF1-10

2001

N. N. Gorelenkov, S. Bernabei,
C. Z. Cheng, G. Y. Fu, K. Hill, S.
Fast Particle Effects on the Internal Kink,
Kaye, G. J. Kramer, Y. Kusama,
Fishbone and Alfvén Modes
K. Shinohara, R. Nazikian, T.
Ozeki, and W. Park

Princeton Plasma Physics
Laboratory

Report No. PPPL-3512 (2001)

2000-JF1-05

29

2001

D. R. Mikkelsen, H. Shirai, N.
Asakura, T. Fujita, T. Fukuda,
Correlation between core and pedestal
T. Hatae, S. Ide, A. Isayama, Y.
temperatures in JT-60U: Experiment andKamada, Y. Kawano, Y. Koide,
modeling
O. Naito, Y. Sakamoto, T.
Takizuka, and H. Urano

Princeton Plasma Physics
Laboratory

Report No. PPPL-3512 (2001)

2001-JF1-04

30

2002

S. Ohsaki, N. Shatashvili, Z.
Yoshida and S. M. Mahajan

570 (2002) 395-407

2000-JF1-09

28

Asymptotic analysis and renormalized
perturbation theory of the non-Hermitian
dynamics of an inviscid vortex

Energy transformation mechanism in the
Solar atmosphere associated withmagnetofluid Coupling: Explosive anderuptive events

Astrophys. J.

A−57

31

2002

Swadesh M. Mahajan,
Komunela I. Nikol’skaya, Nana Generation of flows in the solar atmosphere
Astrophys. J.
L. Shatashvili, and Zensho
due to magnetofluid coupling
Yoshida32

2002

Y. Todo, H. L. Berk, and B. N.
Breizman

Simulation study of beam ion loss due to
Alfvén eigenmode bursts

33

2002

G. Rewoldt, K.W. Hill, R.
Nazikian, W.M. Tang, H.
Shirai, Y. Sakamoto, Y.
Kishimoto, S. Ide, and T.
Fujita34576 (2002) L161-164

2001-JF1-09

Report No. NIFS-749 (2002)

2001-JF2-05

Radial patterns of instability and transport in
Nucl. Fusion
JT-60U internal transport barrier discharges

42-4 (2002) 403-411

2000-JF1-03

2002

W. Horton, F. Porcelli, P. Zhu,
Ignitor physics assessment and confinement
A. Aydemir, Y. Kishimoto, andNucl. Fusion
projects
T. Tajima

42 (2002) 169-179

2001-JF1-08

2002

K. Shinohara, M. Takechi, M.
Ishikawa, Y. Kusama, N. N.
Gorelenkov, C. Z. Cheng, A.
Recent progress of Alfvén eigenmode
Morioka, N. Oyama, K. Tobita, experiments using N-NB in JT-60U tokamak
T. Ozeki, G. J. Kramer, and R.
Nazikian

42 (2002) 942–948

2001-JF2-05

36

2002

G. Rewoldt, L.-P. Ku, W.M.
Tang, H. Sugama, N.
Microinstability studies for the Large Helical
Nakajima, K. Y. Watanabe, S.
Nuclear Fusion
DeviceMurakami, H. Yamada, andW. A. Cooper

42 (2002) 1047-1054

2001-JF1-06

37

2002

A. Ito, Z. Yoshida, T. Tatsuno, Kelvin-Helmholtz instability in Beltrami
S. Ohsaki, and S.M. Mahajan fields

9-12 (2002) 4856-4862

2001-JF1-09

38

2002

Y. Kishimoto, T. Masaki, andT. TajimaHigh energy ions and nuclear fusion in laserPhys. Plasmas
plasma interaction

9 (2002) 589-601

2001-JF2-04

39

2002

V. I. Berezhiani, S. M.
Mahajan, Z. Yoshida, and M.
PekkerDynamics of self-trapped singular beams in
an underdense plasma

Phys. Rev. E

65-4 (2002) 046415

2001-JF1-09

40

2002

Z. Yoshida and S. M. Mahajan

Variational principles and self-organizationin two-fluid plasmas

Phys. Rev. Lett.

88-9 (2002) 095001-1-4

2001-JF1-09

41

2002

V. I. Berezhiani, S. M.
Mahajan, Z. Yoshida, and M.
OhhashiSelf-trapping of strong electromagnetic
beams in relativistic plasmas

PHYSICAL REVIEW E

65 (2002) 047402

2000-JF1-01

42

2003

Oleg Batishchev, Ritoku
Horiuchi

Scope of Simulation Sciencea special issue of Computer
Physics Communications Journal(UK)
http://web.mit.edu/ned/ICNSP/ab
stracts.html

about 75 refereed articles( 400 pages )2003-JF1-05

43

2003

Z. Yoshida, S. Ohsaki, A. Ito,and S. M. Mahajan

Stability of Beltrami flows

J. Math. Phys.

44 (2003) 2168

2003-JF1-10

44

2003

M. Yagi

Report of US-Japan JIFT Workshop on
Structures and Self-Organization in
Turbulent Plasmas and Fluids

Journal of Plasma and Fusion
Research

79 (2003) 1197

2003-JF1-06

2003

D. R. Mikkelsen, H. Shirai, H.
Urano, T. Takizuka, Y.
Kamada, T. Hatae. Y. Koide,
Stiff temperature profiles in JT-60U ELMy HN. Asakura, T. Fujita, T.
Nucl. Fusionmode plasmas
Fukuda, S. Ide, A. Isayama, Y.
Kawano, O. Naito, and Y.
Sakamoto

43 (2003) 30

2001-JF1-04

35

45

NIFS

Nucl. Fusion

Phys. Plasmas

A−58

46

2003

H. Takenaga, S. Higashijima,
N. Oyama, L.G. Bruskin, Y.
Koide, S. Ide, H. Shirai, Y.
Relationship between particle and heat
Sakamoto, T. Suzuki, K.W.
transport in JT-60U plasmas with internal
Hill, G. Rewoldt, G.J. Kramer,transport barrier
R. Nazikian, T. Takizuka, T.
Fujita, A. Sakasai, Y. Kamada,H. Kubo, and JT-60 Team

47

2003

H. Sugama, T.-H. Watanabe,
and W. Horton

48

2003

49

43 (2003) 1235-1245

2000-JF1-04

Comparison between kinetic and fluid
simulations of slab ion temperature gradient Phys. Plasmas
driven turbulence

10 (2003) 726

2001-JF2-08
2002-JF2-2
2002-JF2-10

H. Sugama, T.-H. Watanabe,
and W. Horton

Comparison between kinetic and fluid
simulations of slab ion temperature gradient Phys. Plasmas
driven turbulence

10 (2003) 726-736

2002-JF1-10

2003

Y. Todo, H. L. Berk, and B. N.
Breizman

Simulation of intermittent beam ion loss in a
Physics of Plasmas
Tokamak Fusion Test Reactor experiment10-7 (2003) 2888-2902

2000-JF1-09

50

2004

Structure formation and dynamical behavior
R. Horiuchi, H. Ohtani, and A.
Computer Physics
of kinetic plasmas controlled by magnetic
Ishizawa
Communications
reconnection

164 (2004) 17-32

2004-JF1-16

51

2004

Steve Jardin, Atsushi
Fukuyama

Theory-Based Modeling and Integrated
Simulation of Burning Plasma (ϩ)

http://w3.pppl.gov/usjapanim

2004-JF1-09

52

2004

Noriyoshi Nakajima, Donald
MonticelloProgress of Theoretical Analyses in Three
Dimensional Configuration

http://www.center.iae.kyotou.ac.jp/kondok/meetings/jift/presentations.html

2004-JF1-01

53

2004

Guoyong Fu, Yasushi Todo

Physics of Energetic Particles

http://www.mfescience.org/TTF2005/

2004-JF1-08

54

2004

Y. Todo, H. L. Berk, and B. N.
Breizman

Energetic ion transport due to Alfvén
eigenmode bursts

Journal of Plasma and Fusion
Research SERIES

6 (2004) 69–73

2004-JF1-12

55

2004

S. Ohsaki and S. M. Mahajan

Hall current and Alfvén wave

Phys. Plasmas

11 (2004) 898

2003-JF1-10

56

2004

E. Hameiri and R. Torasso

Linear stability of static equilibrium states inPhys. Plasmas
the Hall-magnetohydrodynamics model

11 (2004) 4934

2004-JF1-05

57

2004

C. Chiu, W. Horton, and Y.
OhsawaLarge acceleration of electrons by the
microstructure of quasi-normal shocks

submitted for publication

2004-JF1-14

58

2004

S. I. Krasheninnikov, Y.
Tomita, R. D. Smirnov, and R. On dust dynamics in tokamak edge plasmas Physics of Plasmas
K. Janev

11 (2004) 3141 (10p)2003-JF1-04

59

2004

E. Hameiri

to be submitted for publication

2004-JF1-05

60

2005

J. Ramos et al.

50-8 (2005) UP1-5

2005-JF1-05

61

2005

Atsushi Fukuyama, Steven
Jardin62

2005

Donald Monticello, Noriyoshi Issues in Theoretical Analyses for Three
Dimensional Configurations
Nakajima

Nuclear Fusion

Phys. Plasmas

Linear Stability of a Hall-MHD Equilibriumwith Discontinuity

Bull. Am. Phys. Soc.

Integrated Modeling of Multi-Scale Physics
in Fusion Plasmas

http://pbsi.nucleng.kyotou.ac.jp/bpsi/usjws3/index.html

2005-JF1-02

http://w3.pppl.gov/~shudson/JIFT/2006/JIFT2006.html

2005-JF1-06

A−59

63

2005

Ritoku Horiuchi, Oleg
Batishchev

New Development of Simulation Science

http://www.tcsc.nifs.ac.jp/icnsp/U
S-JapanSimulationWorkshop.html.

64

2005

M. S. Chu and K. Ichiguchi

Effect of the Resistive Wall on the Growth
Rate of Weakly Unstable External Kink Mode Nucl. Fusionin General 3D Configurations

65

2005

E. Hameiri, A. Ishizawa, and
A. Ishida

Waves in the Hall-Magnetohydrodynamics
Model

66

2005-JF1-03

45 (2005) 804–813

2004-JF1-06

12-7 (2005) 072109-1-13

2004-JF1-05

2005

R. Nazikian, K. Shinohara, G.J.
Kramer, E. Valeo, K. Hill, T.S. Measurement of Turbulence Decorrelation
Hahm, G. Rewoldt, S. Ide, Y. during Transport Barrier Formation in a High Phys. Rev. Lett.
Koide, Y. Oyama, H. Shirai, W. Temperature Fusion PlasmaTang

94 (2005) 135002

2004-JF1-04

67

2005

P. H. Diamond, S.-I. Itoh, K.
Itoh and T. S. Hahm

Zonal Flows in Plasma—A Review

Plasma Physics and Controlled
Fusion47 (2005) R35-R161

2003-JF1-05

68

2005

Ritoku Horiuchi, Oleg
Batishchev

New Development of Simulation Science

special issue of Journal of Plasma
Physics (UK)include about 120 refereed articles

2005-JF1-03

69

2006

Noriyoshi Nakajima, Donald
A. Spong

Progress of Extended MHD Models

http://www.dss.nifs.ac.jp/todo/US-Japan2007/

70

2006

H. Miura, N. Nakajima, T.
Hayashi, and M. Okamoto

Vortical toroidal and compressible motions
in 3D MHD simulations of LHD

J. Plasma Phys

72 (2006) 1095-1099

2005-JF1-10

71

2006

Multi-Scale Approach to the Solution of
K. Ichiguchi and B. A. Carreras Nonlinear MHD Evolution of Heliotron
PlasmaJournal of Plasma Physics

72 (2006) 1117-1121

2005-JF1-10

72

2006

S. Murakami et al.

A global simulation study of ICRF heating in
the LHD

Nucl. Fusion

46 (2006) S425¬S432

2005-JF1-08

73

2007

H. Miura, N. Nakajima, T.
Hayashi and M. Okamoto

Nonlinear Evolution of MHD Instability in
LHD

Fusion Science and Technology

51 (2007) 8-19

2005-JF1-10

74

2007

F. L. Waelbroeck, J. W. Van
Dam, Ritoku Horiuchi

Numerical simulation of complex plasmas

http://workshops.ph.utexas.edu/s
sw/index.php

2007-JF1-7

75

2007

Donald B. Batchelor, Atsushi
Fukuyama

Integrated Modeling of Multi-Physics in
Fusion Plasmas ϩ

http://www.cswim.org/meetings/
us-japan-2007/

2006-JF1-06

76

2007

D. A. Spong, J. H. Harris, A. S.
Shear Flow Generation in Stellarators–
Ware, S. P. Hirshman and L.
Configurational Variations
A. Berry

77

2007

78

79

Phys. Plasmas

2006-JF1-01

Nucl. Fusion

47 (2007) 626-633

2006-JF1-04

S. Toda, K. Itoh, A. Fujisawa,
S.-I. Itoh, M. Yagi, A.
Fukuyama, P.-H. Diamond,and K. Ida

Transport analysis of the effect of zonal
flows on electron internal transport barriers Nucl. Fusion
in toroidal helical plasmas

47 (2007) 914-919

2007-JF1-11

2007

M. Furukawa and L.-J. Zheng

Alfven resonance effect on the error-fieldinduced magnetic islands in rotatingplasmasNucl. Fusion

submitted

2007-JF1-5

2007

A. Ito, J.J. Ramos and N.
Nakajima

Ellipticity of axisymmetric equilibria withflow and pressure anisotropy in single-fluidand Hall magnetohydrodynamics

Phys. Plasmas

14 (2007) 062502

2005-JF1-05

A−60

Electron surface acceleration on a solid
capillary target inner wall irradiated withultra-intense laser pulses

14 (2007) 053112

2006-JF1-02
2007-JF1-02
2007-JF1-10

Physics of Plasmas

14 (2007) 092110-092110-10

2006-JF1-03

Physics of Plasmas

14-2 (2007) 022502-1-18

2007-JF2-7

Electron surface interaction on a solid
capillary inner surface irradiated with ultra- Physics of Plasmas
intense laser pulses

to be published2006-JF1-02

Transport Modeling of Edge Plasma in an
m/n=1/1 Magnetic Island

48 (2008) 106-110

2006-JF1-13

80

2007

T. Nakamura, K. Mima, H.
Sakagami, and T. Johzaki

81

2007

B. N. Rogers, S. Kobayashi, P.
Gyrokinetic Simulations of Collisionless
Ricci, W. Dorland, J. Drake,
Magnetic Reconnection
and T. Tatsuno

82

2007

H. Sugama, T.-H. Watanabe,
and W. Horton

Collisionless kinetic-fluid model of zonal
flows in toroidal plasmas

83

2007

T. Nakamura, K. Mima, et al.

84

2008

R. Kanno, M. Nunami, S.
Satake, H. Takamaru and M.
Okamoto85

2008

Gennady Shvets, and Kunioki Theory and Simulation on Ultra-Intense
Mima
Laser Plasmas

http://peaches.ph.utexas.edu/ifs/j
ift2008-intenselaser.html

2008-JF1-3

86

2008

Alex Arefiev, Hiroaki Ohtani

Progress of Multi-Scale Simulation Models

http://peaches.ph.utexas.edu/ifs/j
ift2008-simulationmodels.html

2008-JF1-1

87

2008

Y. Todo, G. Y. Fu

Energetic Particle Physics in Toroidal
Plasmashttp://www.dss.nifs.ac.jp/todo/US-Japan2008

2008-JF1-9

88

2008

S. M. Mahajan and H. Miura

Linear superposition of nonlinear wave

J. Phys. Plasmas

89

2008

G. Kawamura and A.
Fukuyama

90

2008

91

Phys. Plasmas

Contributions to Plasma Physics

10 (2008) 1-8

2005-JF1-10

Refinement of the gyrokinetic equations forPhys. Plasmasedge plasmas with large flow shear

15 (2008) 042304

2006-JF1-06

T. Cho, V. P. Pasthukov, W.
Horton, T. Mumakura, M.
Hirata, J. Kohagura, N. V.
Chudin, and J. Pratt

Active Control of Internal Transport Barrier
Formation Due to Off-Axis ElectronCyclotron Heating in Gamma 10
Experiments

15 (2008) 056120

2008-JF1-12

2008

Y. Todo, N. Nakajima, M.
Osakabe, S. Yamamoto, and
D. A. Spong

Simulation Study of Energetic Ion Transport
Plasma and Fusion Researchdue to Alfven Eigenmodes in LHD Plasma

3 (2008) S1074

2006-JF1-04

92

2008

R. Kanno, M. Nunami, S.
Satake, H. Takamaru, Y.
Tomita, K. Nakajima, M.
Okamoto and N. Ohyabu

Monte-Carlo Simulation of NeoclassicalTransport in Magnetic Islands and Ergodic
Regions

Plasma and Fusion Research

3 (2008) S1060

2006-JF1-13

93

2008

K. Ichiguchi and B. A. Carreras

Mercier Stability Improvement in Nonlinear
Plasma and Fusion Research
Development of LHD Plasma

3 (2008) S1033

2007-JF1-09

94

2008

Benchmark Tests of Fusion Plasma
T.-H. Watanabe, Y. Todo, and Simulation Codes for Studying
W. Horton
Microturbulence and Energetic-Particle
Dynamics

3 (2008) 061

2008-JF1-12

Phys. Plasmas

Plasma and Fusion Research

A−61

2009

Y. Todo, S. Murakami, T.
Yamamoto, A. Fukuyama, D.
A. Spong, S. Yamamoto, M.
Osakabe, and N. Nakajima

96

2009

K. Toi, M. Isobe, M. Osakabe,
F. Watanabe, K. Ogawa, S.
Yamamoto, N. Nakajima, D.A.
Spong, K. Ida, T. Ido, T. Ito, S.
Morita, K. Nagaoka, K.
MHD Modes Destabilized by Energetic Ions
Narihara, M. Nishiura, S.
on LHD
Ohdachi, S. Sakakibara, A.
Shimizu, K. Tanaka, Y. Todo,
T. Tokuzawa, A. Weller and
LHD Experiment Group

Fusion Science and Technology

97

2009

H. Ohtani and A. Arefiev

http://www.dss.nifs.ac.jp/ohtani/J
IFT2009/

98

2009

Multi-Scale MHD Simulation Incorporating
K. Ichiguchi and B. A Carreras Pressure Transport Equation for LHD
PlasmasJ. Plasma Fusion Res. SERIES

8 (2009) 1171-1175

2007-JF1-9

99

2009

H. Ohtani, W. Horton, T.
Petrosky, and R. Horiuchi

J. Plasma Fusion Res. SERIES

8 (2009) 203-207

2008-JF1-12

100

2009

Y. Nagashima, S.-I. Itoh, K.
Itoh, A. Fujisawa, S. Inagaki, Y.
Kawai, S. Shinohara, M.
Reynolds Stress Measurements for
Fukao, T. Yamada, K.
Investigation of Nonlinear Processes of
J. Plasma Fusion Res. SERIES
Terasaka, T. Maruta, K.
Turbulence in the Large Mirror Device and in
Kamatak, H. Arakawa, M.
the Large Mirror Device-Upgrade
Yagi,N. Kasuya, G. Tynan, P.
H. Diamond, and Y. Takase

8 (2009) 50-54

2009-JF-2

101

2009

D. A. Spong, Y. Todo, M.
Osakabe, L. Berry, B. N.
Energetic particle physics issues for threeBreizman, D. L. Brower, C. B. dimensional toroidal configurations
Deng, A. Konies, E. D’Azevedo

submitted

2006-JF1-04

102

2009

M. Furukawa and L. J. Zheng

Suppression of error-field-induced magnetic
islands by Alfvén resonance effect inNuclear Fusion
rotating plasmas

49 (2009) 075018 (6 pp)

2008-JF1-6

103

2009

T. S. Hahm, Lu Wang, and J.
MadsenFully electromagnetic nonlinear gyrokinetic
equations for tokamak edge turbulencePhys. Plasmas

16 (2009) 022305

2007-JF1-1

104

2009

M. Furukawa, S. Tokuda, and A numerical matching technique for
L. J. Zheng
resistive magnetohydrodynamics modes

Phys. Plasmas

17 (2010) 052502

2008-JF1-6

105

2009

H.B. Cai, K. Mima, W.M.
Zhou, T. Jozaki,1 H.
Nagatomo, A. Sunahara, R.J.
Mason

Enhancing the Number of High-Energy
Electrons Deposited to a Compressed Pellet Phys. Rev. Lett.
via Double Cones in Fast Ignition

102 (2009) 245001

2009-JF-7

106

2009

S. Takahashi, H. Kawai, Y.
Ohsawa, S. Usami, C. Chiu,
and W. Horton

The effect of parallel electric field in shockwaves on the acceleration of relativistic
ions, electrons, and positrons

Physics of Plasmas

16-11 (2009) 112308-1-10

2009-JF-3

107

2009

A. Arefiev

Generation of fast ions by microclusters

Plasma and Fusion Research

accepted for publication

2009-JF-10

108

2009

T. Johzaki, Y. Sentoku, et al.

Core heating properties in FIREX-I influence of cone tip

Plasma Phys. Control. Fusion

51 (2009) 014002 (15pp)

2009-JF-5

95

Numerical Analyses of Energetic Particles in
Fusion Science and Technology
LHD

Advanced Simulation Methods in Plasmas

Energy Conversion in Magnetic
Reconnection with Chaos Diffusion

Nucl. Fusion

A−62

submitted

2008-JF1-9

submitted

2008-JF1-9

2009-JF-8

109

2010

D. A. Spong, B. N. Breizman,
D.L. Brower, E. D’Azevedo, C. Energetic particle-driven instabilities in
B. Deng, A. Konies, Y. Todo,
general toroidal configurations
and K. Toi

Contributions to Plasma Physics

50 (8) (2010) 708-712

2006-JF1-1

110

2010

K. Toi, M. Isobe, M. Osakabe, Overview of Studies on Energetic Ion Driven
K. Ogawa, D. Spong, Y. Todo, MHD Instabilities in Stellarator/Helical
Contributions to Plasma Physics
and LHD Experiment Group
Plasmas and Comparison with Tokamaks

50 (6-7) (2010) 493-500

2006-JF1-1

111

2010

Paul Bonoli and Atsushi
Fukuyama

Integrated Modeling and Simulation in
Toroidal Plasmas

112

2010

D. A. Spong, E. D'Azevedo,
and Y. Todo

Clustered frequency analysis of shear Alfvén
Physics of Plasmas
modes in stellarators

113

2010

Formation of coherent vortex streets and
M. Natata, T.-H. Watanabe, H.
transport reduction in electron temperature Physics of Plasmas
Sugama, and W. Horton
gradient driven turbulence

114

2010

S. R. Hudson and N. Nakajima

Pressure, chaotic magnetic fields and MHD
equilibria

115

2010

K. Saito, K. Ichiguchi, and N.
OhyabuInteraction between static magnetic islands
and interchange modes in a straightPhys. Plasmas
heliotron plasma with high resistivity

http://www.psfc.mit.edu/JIFT09/JI
FT09.html

2009-JF-1

17 (2010) 022106

2006-JF1-1

17-4 (2010) 042306-1-13

2008-JF1-12

17 (2010) 052511

2009-JF-9

17, 6 (2010) 062504-1-14

2007-JF1-9

Month Date, Year, Place, CountryYear-Category-No.

October 4-10, 2000, Sorrento, Italy

2000-JF1-09

The 18th International Conferenceon Plasma Physics and Controlled October 4-10, 2000, Sorrento, Italy
Nuclear Fusion Research

2000-JF1-05

The 17th Conference

October 18-24, 1998, Yokohama
Japan(IAEA, Vienna, 1999)

2000-JF1-05

Physics of Plasmas

2.ConferencePaper
No

Year

Authors

Title of Paper

Conference Name

1

2000

Y. Todo, T.-H. Watanabe, H.B. Park, and T. Sato

2

2000

N. N. Gorelenkov, S. Bernabei,
C. Z. Cheng, G. Y. Fu, K. Hill, S.
Fast Particle Effects on the Internal Kink,
Kaye, G. J. Kramer, Y. Kusama,
Fishbone and Alfvén Modes
K. Shinohara, R. Nazikian, T.
Ozeki, and W. Park

3

2001

Y. Todo and T. Sato

4

2001

C. Z. Cheng, N. N. Gorelenkov,
G. J. Kramer, R. Nazikan, Y.
N-NBI excitation of frequency chirping
Kusama, K. Shinohara, and T. modes in JT-60U experiments
Ozeki

The 7th IAEA Technical Committee
Meeting on Energetic Particles in
Magnetic Confinement Systems

October 8-11, 2001, Gothenberg,
Sweden2001-JF2-05

5

2001

K. Shinohara, M. Takechi, M.
Ishikawa, Y. Kusama, N. N.
Gorelenkov, C. Z. Cheng, A.
Recent progress of Alfvén eigenmode
Morioka, N. Oyama, K. Tobita, experiments using NNB in JT-60U tokamak
T. Ozeki, G. J. Kramer, and R.
NazikianThe 7th IAEA Technical Committee
Meeting on Energetic Particles in
Magnetic Confinement Systems

Oct. 8-11, 2001, Gothenberg,
Sweden2001-JF2-05

6

2002

S. M. Mahajan, R.
D.Hazeltine, and Z. Yoshida

General Fluid Theories, Variational Principles 19th IAEA Fusion Energy
and Self-Organization
Conference

October 14-19, 2002, Lyon, France

2001-JF1-09

7

2002

Y. Todo, H. L. Berk, and B. N.
Breizman

Simulation study of beam ion loss due to
Alfvén eigenmode bursts

October 14-19, 2002, Lyon, France

2002-JF2-19

Fokker-Planck Simulation Study of Alfvén
Eigenmode Burst

18th IAEA Fusion Energy
Conference

Kinetic-magnetohydrodynamic simulation
study of fast ions and toroidal Alfvén
eigenmode

19th IAEA Fusion Energy
Conference

A−63

2002

H. Naitou, T. Kobayashi, M.
Yagi, T. Matsumoto, S.
Interaction between MHD modes andTokuda, Y. Kishimoto, and J.- vortexes
N. Leboeuf

6th Kyushu-Okinawa-Yamaguchi
Branch Division Meeting of Japan
Society of Plasma Science andNuclear Fusion Research

December 13, 2002, Saga, Japan

2001-JF2-01

2002

Y. Sakamoto, T. Suzuki, S. Ide,
Y. Koide, H. Takenaga, Y.
Kamada, T. Fujita, T. Fukuda, Properties of Internal Transport Barrier
T. Takizuka, H. Shirai, N.
Formation in JT-60U
Oyama, Y. Miura, K.W. Hill, G.
Rewoldt, and JT-60 TeamThe 19th International Atomic
Energy Agency's (IAEA) Fusion
Energy Conference 2002 (CN-94)

October 14-19, 2002, Lyon, France

2000-JF1-04

2002

H. Takenaga, S. Higashijima,
N. Oyama, L.G. Bruskin, Y.
Koide, S. Ide, H. Shirai, Y.
Relationship between particle and heat
Sakamoto, T. Suzuki, K.W.
transport in JT-60U plasmas with internal
Hill, G. Rewoldt, G.J. Kramer,transport barrier
R. Nazikian, T. Takizuka, T.
Fujita, A. Sakasai, Y. Kamada,H. Kubo, and JT-60 TeamThe 19th International Atomic
Energy Agency's (IAEA) Fusion
Energy Conference 2002 (CN-94)

October 14-19, 2002, Lyon, France

2000-JF1-04

11

2002

K.W. Hill, D.R. Ernst, D.
Mikkelsen, G. Rewoldt, S.
Higashijima, N. Asakura, H.
Shirai, T. Takizuka, S.
Konoshima, Y. Kamada, H.
Kubo, and Y. Miura

Study of Integrated High-Performance
Regimes with Impurity Injection in JT-60U
Discharges

The 19th International Atomic
Energy Agency's (IAEA) Fusion
Energy Conference 2002 (CN-94)

October 14-19, 2002, Lyon, France

2001-JF1-04

12

2002

H. Yamada, S. Murakami, etal.

Response of Density and Temperature
Profiles to Heat Deposition Profile and Its
Impact on Global Scaling in LHD

The 19th International Atomic
Energy Agency's (IAEA) Fusion
Energy Conference 2002 (CN-94)

October 14-19, 2002, Lyon, France

2002-JF2-02
2002-JF2-07

13

2002

M. Yokoyama, K. Itoh, S.
Okamura, K. Matsuoka, N.
Nakajima, S.-I. Itoh, G.H.
Drift Reversal Capability in Helical Systems
Neilson, M.C. Zarnstorff, and
G. Rewoldt

The 19th International Atomic
Energy Agency's (IAEA) Fusion
Energy Conference 2002 (CN-94)

October 14-19, 2002, Lyon, France

2002-JF2-20
2002-JF2-8

14

2003

Ishida, H. Caesar, L. C.
Improved Formalism for Flowing Two-Fluid
Steinhauer, and Y.-K. M. Peng Equilibrium and Its Application to ST

The 13th International Toki
Conference on Plasma Physics andControlled Nuclear Fusion

December 9-12, 2003, Toki, Japan

2003-JF1-03

15

2003

S. I. Krasheninnikov, D. D.
Ryutov, and G. Yu

Large plasma pressure perturbations andradial convective transport in a tokamak

The 13th International Toki
Conference on Plasma Physics andControlled Nuclear Fusion

December 9-12, 2003, Toki, Japan

2003-JF1-04

16

2003

T.-H. Watanabe, H. Sugama,
W. Horton, and H.V. Wong

A non-dissipative closure model for mirror
instability in a collisionless plasma

The 2003 International Sherwood
Fusion Theory Conference

April 28-30, 2003, Texas, USA

2002-JF1-10

17

2003

S. I. Krasheninnikov

Blobs in edge plasmas

The Meeting on Advances in
Nonlinear Fluid and Plasma
Dynamics

December 3-4, 2003, Kyushu
University, Japan

2003-JF1-04

18

2003

The US-Japan JIFT Workshop on
S. I. Krasheninnikov, Y.
Theory-based Modeling andTomita, R. D. Smirnov, and R. On dust dynamics in tokamak edge plasmas
Integrated Simulation of Burning
K. Janev
PlasmasDecember 15-17, 2003, Kyoto, Japan

2003-JF1-04

8

9

10

A−64

19

2003

H. Naitou, J.-N. Leboeuf, H.
Nagahara, T. Kobayashi, M.
Yagi, T. Matsumoto, S.
TokudaU.S.-Japan Joint Institute for
Vortex Generation and Collisionless Internal Fusion Theory Workshop on
Kink Mode in Tokamaks
Structures and Self-Organizationin Turbulent Plasmas and Fluids

September 19, 22-23, 2003, San
Diego, USA

2003-JF1-08

20

2004

A. Fukuyama et al.

Advanced Transport Modeling of Toroidal
Plasmas with Transport Barriers

20th IAEA Fusion Energy
Conference

November 1-6, 2004, Vilamoura,
Portugal

2004-JF1-09

21

2004

M. Yagi, S. Yoshida, S.-I. Itoh,H. Naitou, H. Nagahara, J.-N. Nonlinear simulation of tearing mode andLeboeuf, K. Itoh, T.
m=1 internal kink mode based on kinetic
Matsumoto, S. Tokuda, and RMHD model
M. Azumi

The 20th IAEA Fusion Energy
Conference

November 1-6, 2004, Vilamoura,
Portugal

2003-JF1-08

22

2006

K. Ichiguchi and B. A. Carreras Multi-Scale Simulation of Heliotron Plasma

Joint Workshop of NIFS
Cooperative Programs 2006 for
MHD Theory and Related Topics

September 14-15, 2006, Toki, Japan

2006-JF2-08

23

2007

H. Ohtani, R. Horiuchi, and W. Three dimensional particle simulations of
Hortondriven magnetic reconnection

2007 International Sherwood
Fusion Theory Conference

April 23-25, 2007, Annapolis, USA

2006-JF1-12

24

2007

H. Ohtani, R. Horiuchi, W.
Horton, and T. Petrosky

March 26-29, 2007, St.Michaels, USA

2006-JF1-12

25

2007

Dynamics of magnetic dissipation region in
H. Ohtani, R. Horiuchi, and W.
collisionless driven reconnection in open
Hortonsystem20th International Conference on
Numerical Simulation of Plasmas

October 10-12, 2007, Austin, USA

2006-JF1-12

26

2007

J. Pratt and W. Horton

49th American Physical Society
Drift Waves and Stability in the GAMMA-10 Division of Plasma Physics Annual
MeetingNovember 12-16, 2007, Orlando,USA

2007-JF1-4

27

2007

J. Pratt, W. Horton, J-H. Kim,and H. L. Berk

Drift Wave Fluctuation in Tandem Mirrors
with Anchor Cells and Sheared Flows

International Sherwood Fusion
Theory Conference

April 23¬25, 2007, Annapolis, USA

2007-JF1-4

28

2007

R. Kanno, M. Nunami, S.
Satake, H. Takamaru and M.
OkamotoTransport Modeling of Edge Plasma in an
m/n=1/1 Magnetic Island

The 11th International Workshop
on Plasma Edge Theory in Fusion
Devices23-25 May 2007, Takayama, Japan

2006-JF1-13

29

2007

R. Kanno, M. Nunami, S.
Satake, H. Takamaru, Y.
Tomita, K. Nakajima, M.
Okamoto and N. Ohyabu

Monte-Carlo Simulation of NeoclassicalTransport in Magnetic Islands and Ergodic
Regions

The Joint Conference of 17th
International Toki Conference(ITC) on Physics of Flows andTurbulence in Plasmas and 16th
International Stellarator/Heliotron
Workshop (ISHW) 2007

15-19 October 2007, Toki, Japan

2006-JF1-13

30

2007

W. Horton, J.-H. Kim, E. Asp,
T. Hoang, T.-H. Watanabe,and H. Sugama

Drift Wave Turbulence

Turbulent Transport in Fusion
Plasmas, First ITER International
Summer School

July 16-20, 2007,Aix-en-Provence,France2007-JF1-1

31

2007

Atsushi Ito, Jesus. J. Ramos,
and Noriyoshi Nakajima

Workshop of NIFS Cooperative
High-beta axisymmetric equilibria with flow
Programs 2007 ‘Progress of MHD
in reduced single-fluid and two-fluid models
Theory and Related Topics’

1-2 November, 2007, Toki, Japan

2005-JF1-05

32

2007

Noriyoshi Nakajima, Satoru
Sakakibara, Kiyomasa
Watanabe, Stuart Hudson,
and Chris Hegna

Analysis of MHD stability in high-beta
plasmas in LHD

Workshop of NIFS Cooperative
Programs 2007 ‘Progress of MHD
Theory and Related Topics’

1-2 November, 2007, Toki, Japan

2005-JF1-06

Energy release between fields and particles,
2007 US-Japan Workshop on
and change of velocity distribution in
Magnetic Reconnection
collisionless driven reconnection

A−65

Workshop of NIFS Cooperative
Mercier Stability Improvement in Nonlinear
Programs 2007 ‘Progress of MHD
Development of Heliotron Plasma
Theory and Related Topics’

33

2007

K. Ichiguchi and B. A Carreras

34

2008

Tearing mode stability analysis via a new
M. Furukawa, S. Tokuda, andnumerical matching technique for resistive
L.-J. Zheng
MHD

35

2008

H. Ohtani, W. Horton. T.
Petrosky, and R. Horiuchi

36

2008

37

1-2 November, 2007, Toki, Japan

2007-JF1-09

50th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

November 17-21, 2008, Dallas, USA

2008-JF1-6

Energy Conversion in Magnetic
Reconnection with Chaos Diffusion

2008 International Congress on
Plasma Physics

September 8-12, 2008, Fukuoka,Japan

2006-JF1-12

H. Ohtani, R. Horiuchi, W.
Horton, and T. Petrosky

Energy release in Magnetic Reconnection
with Chaos Diffusion

2008 International Sherwood
Fusion Theory Conference

March 30 - April 2, 2008, Boulder,USA

2006-JF1-12

2008

A. H. Glasser

Preconditioning and Scalability of Implicit
20th International Conference on
Extended MHD Plasma Simulation by FEETINumerical Simulation of Plasmas
DP Domain Substructuring

October 10-12, 2008, Austin, USA

2007-JF1-6

38

2008

Y. Todo, M. Osakabe, et al

Simulation Study of Interaction between
Energetic Ions and Alfven Eigenmodes in
LHD

October 13-18, 2008, Geneva,
Switzerland

2008-JF1-9

39

2008

M. Furukawa and L.-J. Zheng

Suppression of error-field-induced magnetic
22th IAEA Fusion Energy
islands by Alfvén resonance e ffect inConference
rotating plasmas

Oct. 13-18, 2008, Geneva,
Swizerland

2008-JF1-6

40

2008

T. Johzaki, Y. Sentoku, H.
Sakagami, H. Nagatomo, K.
Mima, and Y. Nakao

Core Heating Properties in FIREX-I –Influence of Cone Tip

35th European Physical Society
Plasma Physics Conference

June 09-13, 2008, Crete, Greece

2007-JF1-10

41

2008

H. Ohtani, W. Horton. T.
Petrosky, and R. Horiuchi

Role of Chaotic Orbits of Meandering
Particles in Magnetic Reconnection

50th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

November 17-21, 2008, Dallas, USA

2008-JF1-12

42

2008

K. Uzawa, T. H. Watanabe, H. Zonal Flows from Parametric Decays in ITG
Sugama, N. Nakajima, and W. Turbulence and the Internal Gravity Wave
HortonParadigm

50th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

November 17-21, 2008, Dallas, USA

2008-JF1-12

43

2008

M. Nakata, T. H. Watanabe,
and W. Horton

Gyrokinetic Analysis of Vortex Structures
and Distribution Functions in Slab ETG
Turbulence

50th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

November 17-21, 2008, Dallas, USA

2008-JF1-12

44

2008

W. Horton and H. Miura

Dust Devil Dynamics

50th Annual Meeting of theDivision of Plasma Physics,
American Physical Society

November 17-21, 2008, Dallas, USA

2008-JF1-12

45

2010

L. Zheng and M. Furukawa

Current-interchange Tearing Modes:
Conversion from Interchange-type Modes to IAEA Fusion Energy Conference
Tearing Modes

11-16 October, 2010, Daejeon, Korea

2009-JF-11

46

2010

S. Murakami, K. Itoh, L.
Simulation Study of Toroidal Flow
Zheng, J. W. Van Dam, and A.
Generation by the ICRF Minority Heating
Fukuyama

11-16 October, 2010, Daejeon, Korea

2009-JF-11

47

2010

W. Horton, O. Yamagishi, and Electron temperature gradient drift mode in The International Sherwood
A. Senthe Columbia Linear Mirror
Fusion Theory Conference

19-21 April, 2010, Seattle,
Washington, USA

2009-JF-6

48

2010

O. Yamagishi, W. Horton, F. L. Numerical study of zonal flow generation
Waelbroeck, P. J. Morrison, with the Hasegawa-Wakatani model andand C. Correa
comparison with linear predictions

13-16 April, 2010, Annapolis,
Maryland, Spain

2009-JF-6

22nd IAEA Fusion Energy
Conference

IAEA Fusion Energy Conference

U.S. Transport Task ForceWorkshop

A−66

CHAPTER5JUPITERII
Task11AFlibeHandling/TritiumChemistry
No

Year

Authors

Title of Paper

Journal(Year) Page (Start) -Page(End) or
Identification No.

1

2001

Sagara, A., Yamanishi H., Uda T.,
Motojima, O., Kunigi, T.,
Matsumoto, Y., Wu, Y., Matsui, H.,
Studies on Flibe Blanket Designs in Helical Reactor
Takahasi, T., Yamamoto, T., Toda, S.,
FFHR
Mitarai, O., Satake, S., Terai, T.,
Tanaka, S., Fukada, S., Nishikawa,
M., Shimizu, A., Yoshida, N.

2

2001

Terai, T., Suzuki, A., Tanaka, S.

Tritium Release from Li2BeF4 Molten Salt Breeder
under Neutron Irradiation at Elevated Temperature

Fusion Technology

39 (2001) 768-772

3

2001

Terai, T., Nishimura, H., Yamaguchi,
K., Yamawaki, M., Suzuki, A.,
Compatibility of Structural Materials with Li2BeF4
Muroga, T., Sagara, A. and
Molten Salt Breeder
Motojima, O.

Fusion Technology

39 (2001) 784-788

4

2001

Nishimura, H., Suzuki, A., Terai, T.,
Chemical Behavior of Li2BeF4 Molten Salt as a Liquid
Yamawaki, M., Tanaka, S., Sagara A.,
Fusion Engineering and Design
Tritium Breeder
and Motojima, O

58-59 (2001) 667-672

5

2002

Petti, D.A., Anderl, R.A., Smolik,
JUPITER-II Flibe Tritium Chemistry and Safety
G.R., Sze, D.-K., Terai T. and Tanaka,
Experimental Program
S.

Fusion Science and Technology

41 (2002) 807-811

6

2002

Fukada, S., Nishikawa, M., Sagara A. Mass-Transport Properties to Estimate Rates ofand Terai, T.
Tritium Recovery from FLIBE Blanket

Fusion Science and Technology

41 (2002) 1054-1058

7

2002

Fukada, S. Anderl, R.A., Hatano, Y.,
Schuetz, S.T., Pawelko, R.J., Petti,
D.A., Smolik, G.R., Terai, T.,
Nishikawa, M., Tanaka S. and
Sagara, A.

Initial Studies of Tritium Behavior in Flibe and Flibefacing Material

Fusion Engineering and Design

61-62 (2002) 783-788

8

2002

Nishimura, H., Terai, T., Yamawaki,
M., Tanaka, S., Sagara A. andMotojima, O.

Compatibility of Ferritic Steels with Li2BeF4 Molten
Salt Breeder

Journal of Nuclear materials

307-311 (2002) 1355-1359

9

2003

Fukada, S., Anderl, R.A., Pawelko,
R.J., Smolik, G.R., Schultz, S.T., O’
Brien, J.E., Nishimura, H., Hatano, Y., FLIBE-D2 Permeation Experiment and Analysis
Terai, T., Petti, D.A., Sze, D.-K. andTanaka, S.

10

2004

Smolik, G., Pawelko, R., Morimoto,Y., Okuno, K., Anderl, R., Petti, D.A.
and Terai, T.

Mobilization Measurements from Flibe under Argon
Journal of Nuclear Materials
and Air Flow329-333 (2004) 1322-1326

11

2004

Anderl, R.A., Fukada, S., Smolik,
G.R., Pawelko, R.J., Schuetz, S.T.,
Deuterium/tritium Behavior in Flibe and Flibe-facing
Sharpe, J.P., Merrill, B.J., Petti, D.A.,
Journal of Nuclear Materials
Materials
Nishimura, H., Terai T. and Tanaka,S.

329-333 (2004) 1327-1331

12

2006

Fukada, S., Morisaki, A., Sagara A.
and Terai, T.

Control of Tritium in FFHR-2 Self-cooled Flibe
Blanket13

2006

Fukada, S., Morisaki, A.

Hydrogen permeability through a mixed molten salt
Journal of Nuclear Materials
of LiF, NaF and KF (Flinak) as a heat-transfer fluid

14

2006

Simpson, M.F., Smolik, G.R., Sharpe,
J.P., Anderl, R.A., Petti, D.A., Hatano, Quantitative Measurement of Beryllium-controlledY., Hara, M., Oya, Y., Fukada, S.,
Redox of Hydrogen Fluoride in Molten Flibe
Tanaka, S., Terai T., and Sze, D.-K

A−67

Fusion Technology

39 (2001) 753-757

Fusion Engineering andTechnology

Fusion Engineering and Design

Fusion Engineering and Design

44 (2003) 410-414

81 (2006) 477-483

358 (2006) 235-242

81 (2006) 541-547

15

2006

Hara, M., Hatano, Y., Simpson, M.F.,
Smolik, G.R., Sharpe, J.P., Oya, Y.,
Okuno, K., Nishikawa, M., Terai, T., Interactions between Molten Flibe and Metallic Be
Tanaka, S., Anderl, R.A., Petti D.A.
and Sze, D.-K

16

2006

Klix, A., Suzuki A. and Terai, T.

17

2006

Kimura, A., Kasada, R., Kohyama, A.,
Konishi, S., Enoeda, M., Akiba, M.,
Ferritic Steel-blanket Systems Integration R&DJitsukawa, S., Ukai, S., Terai T. and Compatibility Assessment
Sagara, A.

Fusion Engineering and Design

81 (2006) 909-916

2006

Sagara, A., Imagawa, S., Tanaka, T.,
Muroga, T., Kubota, Y., Dolan, T.,
Carbon Tiles as Spectral-shifter for Long-life Liquid
Hashizume, H., Kunugi, T., Fukada,Blanket in LHD-type Reactor FFHR
S., Shimizu, A., Terai T. and Mitarai,O.

Fusion Engineering and Design

81 (2006) 1299-1304

2006

Petti, D.A., Smolik, G.R., Simpson,
M.F., Sharpe, J.P., Anderl, R.A.,
Fukada, S., Hatano, Y., Hara, M.,
Oya, Y., Terai, T., Sze, D.-K. andTanaka, S.

JUPITER-II Molten Salt Flibe Research: An Update on
Tritium, Mobilization and Redox Chemistry
Fusion Engineering and Design
Experiments

81 (2006) 1439-1449

20

2007

Fukada, S., Simpson, M.F., Anderl,R.A., Sharpe, J.P., Katayama, K.,
Reaction Rate of Beryllium with Fluorine Ion for
Smolik, G.R., Oya, Y., Terai, T.,
Flibe Redox Control
Okuno, K., Hara, M., Petti, D.A.,
Tanaka, S., Sze, D.-K. and Sagara, A.

Journal of Nuclear Materials

367-370 (2007) 1190-1196

21

2007

Calderoni, P., Sharpe, J.P., Hara M.
and Oya, Y.

Fusion Engineering and Design367-370, Part 2 (2007)
1190-119618

19

Fusion Engineering and Design

81 (2006) 561-566

Study of Tritium Migration in Liquid Li2BeF4 with Ab
Fusion Engineering and Design
initio Molecular Dynamics

81 (2006) 713-717

Measurement of tritium permeation in flibe

Task11BThermofluidCharacteristicsofFlibeSimulant
2001

Chiba, S., Toda, S., Yuki, K. and
Sagara, A.

23

22

Heat Transfer Enhancement for a Molten Salt FLiBe
ChannelFusion Technology

39 (2001) 779-783

2001

Sagara, A., Yamanishi, H., Uda, T.,
Motojima, O., Mitarai, O., Kunugi,T., Matsumoto, Y., Satake, S., Wu, Y.,
Studies in Flibe Blanket Designs in Helical Reactor
Terai, T., Tanaka, S., Matsui, H.,
FFHR
Takahashi, S., Yamamoto, T., Toda,
S., Fukada, S., Nishikawa, M.,
Shimizu, A. and Yoshida, N.

Fusion Technology

39 (2001) 753-757

24

2001

Direct Numerical Simulation of Turbulent FreeKunugi, T., Satake, S. and Sagara, A. Surface High Prandtl Number Fluid Flows in Fusion
Reactors

Nuclear Instruments and Methods
in Physics Research A

464 (2001) 165-171

25

2001/
2002

Smolentsev, S., Abdou, M. A.,
Kunugi ,T., Morley, N. B., Satake, S.
and Ying, A.

Modeling of Liquid Walls in Apex Study

International Journal of Applied
Electro-Magnetics and Mechanics

13 (2001/2002) 373-379

26

2002

Satake, S., Kunugi, T. andSmolentsev, S.

Advances in Direct Numerical Simulation for MHD
Modeling of Free Surface Flows

Fusion Engineering Design

61-62 (2002) 95-102

27

2002

Freeze, B., Dagher, M., Sketchley, T.,
FLIHY experimental facilities for studying open
Morley, N. B., Smolentsev, S. andchannel turbulent flows and heat transfer
Abdou, M. A.

Fusion Engineering Design63-64 (2002) 391-395

28

2002

Smolentsev, S., Freeze, B., Morley,
N. B. and Abdou, M. A.

Experimental study of turbulent supercritical open
channel water flow as applied to the CLiFF concept

Fusion Engineering Design63-64 (2002) 397-403

29

2002

Toda, S., Chiba, S., Yuki, K., Omae,
M. and Sagara, S.

Experimental research on molten salt thermofluid
technology using a high-temperature molten salt
loop applied for a fusion reactor flibe blanket

Fusion Engineering Design63-64 (2002) 405-409.

30

2002

Kunugi, T. and Satake, S.

Approaches of Fusion Science to Global Warmingfrom the Perspective of Thermofluid Research

Fusion Engineering Design63-64 (2002) 665-672

A−68

31

2002

Smolentsev, S., Abdou, M. A.,
Application of the "K-epsilon" model to open
Morley, N. B., Ying, A. and Kunugi, T. channel flows in a magnetic field

International Journal ofEngineering Science

40 (2002) 693-711

32

2002

Freeze, B., Smolentsev, S., Morley,
N. B. and Abdou, M. A.

Characterization of the Effect of Froude Number on
Surface Waves and Heat Transfer in Inclined
Turbulent Open Channel Water Flows

International Journal of Heat andMass Transfer

46 (2002) 3765-3775

33

2002

Satake, S., Kunugi, T. andSmolentsev, S.

DNS of Turbulent Pipe Flow in a Transverse
Magnetic Field

Journal of Turbulence

3 (2002) 020(http://jot.iop.org/)

34

2002

Satake, S., Kunugi, T. andSmolentsev, S.

Direct numerical simulation of MHD turbulent freesurface flow

Transaction JSME

68 (2002) 755-760

35

2004

Smolentsev, S., Morley, N. B.,
Thermofluid Modeling and Experiments for Free
Freeze, B., Miraghaie, R., Nave, J. C.,
Surface Flows of Low-Conductivity Fluid in Fusion
Banerjee, S., Ying, A. and Abdou, M.
SystemsA.

Fusion Engineering Design,

72 (2004) 63-81

36

2005

Chiba, S., Omae, M., Yuki, K.,
Experimental research on heat transfer
Hashizume, H., Toda, S. and Sagara,enhancement for high Prandtl-number fluid
A.

Fusion Science and Technology

47 (2005) 569-573

37

2005

Morley, N. B., Malang, S. andKirillov, I.

Thermofluid Magnetohydrodynamic Issues for
Liquid Breeders

Fusion Science and Technology

47 (2005) 488-501

38

2005

Okumura, M., Yuki, K., Hashizume,
H. and Sagara, A.

Evaluation of Flow Structure in Packed-Bed Tube by
Fusion Science and Technology
Visualization Experiment

47 (2005) 1089-1093

39

2005

Sagara, A., Tanaka, T., Muroga, T.,
Innovative liquid breeder blanket design activities in
Fusion Science and Technology
Hashizume, H., Kunugi, T., Fukada, S.
Japan
and Shimizu, A.

47 (2005) 524-529

40

2005

Smolentsev, S., Miraghaie, R. andAbdou, M. A.

MHD Effects on Heat Transfer in a Molten Salt
Blanket47 (2005) 559-563

41

2005

Smolentsev, S.,and Miraghaie, R.

Study of a Free Surface in Open-Channel Water
International Journal of
Flows in the Regime from weak to strong Turbulence Multiphase Flow

42

2005

Abdou, M. A., Morley, N. B., Ying, A., Overview of fusion blanket R&D in the US over the
Smolentsev, S. and Calderoni, P.
last decade

Nuclear Engineering andTechnology

43

2005/
2006

MHD effect on flow structures and heat transfer
Li, F-Ch., Kunugi, T. and Serizawa, A. characteristics of liquid metal-gas annular flow in a
vertical pipe

International Journal of Heat andMass Transfer

44

2006

Morley, N. B., Abdou, M. A.,
Anderson, M., Calderoni, P., Kurtz,
R. J., Nygren, R., Raffray, R., Sawan, Overview of Fusion Nuclear Technology in the US
M., Sharpe, P., Smolentsev, S.,
Willms, S. and Ying, A.

Fusion Engineering Design

81 (2006) 33-43

45

2006

Satake, S., Kunugi, T., Naito, N. and
Sagara, A.

Direct numerical simulation of MHD flow withelectrically conducting wall

Fusion Engineering Design

81 (2006) 367-374

46

2006

Chiba, S., Yuki, K., Hashizume, H.,
Toda, S. and Sagara, A.

Numerical research on heat transfer enhancement
for high Prandtl-number fluid

Fusion Engineering Design

81 (2006) 513-517

47

2006

Satake, M., Yuki, K., Chiba, S. andHashizume, H.

Numerical analysis of MHD flow structure behind asquare rod

Fusion Engineering Design

81 (2006) 525-532

48

2006

Takeuchi, J., Satake, S., Miraghaie, Study of heat transfer enhancement / suppression
R., Yuki, K., Yokomine, T., Kunugi, T., for molten salt flows in a large diameter circularMorley, N. B. and Abdou M. A.
pipe: Part one – Benchmarking,Fusion Engineering Design

81 (2006) 601-606

49

2006

Direct numerical simulation of turbulent channel
Satake, S., Kunugi. T., Takase, K. andflow under a uniform magnetic field for large-scaleOse, Y.
structures at high Reynolds number

Physics of Fluids

18 (2006) 125106

A−69

Fusion Science and Technology

31 (2005) 921-939

37 (2005) 401-422

48 (2005/2006) 2571-2581

50

2007

Nakaharai, H., Takeuchi, J.,
The influence of a magnetic field on turbulent heat
Yokomine, T., Kunugi, T., Satake, S.,transfer of high Prandtl number fluidMorley, N. B. and Abdou, M. A

Experimental Thermal and Fluid
Science32 (2007) 23-28

51

2007

Takeuchi, J., Satake, S., Kunugi, T.,
Yokomine, T., Morley, N. B., andAbdou, M. A.

Fusion Science and Technology

52 (2007) 860-864

52

2007

Nakaharai, H., Takami, S., Yokomine, Numerical study of heat transfer characteristics in a
Fusion Science and Technology
T., Ebara, S., Shimizu, A.
tube with regularly spaced twisted tape

52 (2007) 855-859

53

2007

Yokomine, T., Takeuchi, J.,
Experimental investigation of turbulent heat
Nakaharai, H., Satake, S., Kunugi, T., transfer of high Prandtl number fluid flow underMorley, N. B., Abdou, M. A.
strong magnetic field

Fusion Science and Technology

52 (2007) 625-629

54

2007

Satoh, T., Yuki, K., Chiba, S.,
Hashizume, H. and Sagara, S.

Heat Transfer Performance for High Prandtl andHigh Temperature Molten Salt Flow in SpherePacked Pipes

Fusion Science and Technology

52 (2007) 618-624

55

2008

Seto, N., Yuki, K., Hashizume, H.,
Sagara, A.

Heat transfer and pressure drop correlations ofsphere-packed pipes for a wide range of Re and Pr

Fusion Engineering and Design

83, 7-9 (2008) 1102-1107

56

2008

Takeuchi, J., Satake, S., Kunugi, T.,
Yokomine, T., Morley, N. B.and
Abdou, M.A.

Experimental study on MHD effects on turbulent
flow of FLIBE stimulant fluid in a circular pipe

Fusion Engineering and Design

83, 7-9 (2008) 1082-1086

57

2008

Y. Yamamoto, T. Kunugi, S. Satake,
S. Smolentsev

DNS and k-epsilon model simulation of MHD
turbulent channel flows with heat transfer

Fusion Engineering and Design

83, 7-9 (2008) 1309-1312

Development of PIV technique under magnetic
fields and measurement of turbulent pipe flow of
FLIBE simulant fluid

Task12AMHDcoatingforV/Lisystems
58

2002

Fujiwara, M., Natesan, K., Satou,
M., Hasegawa, A., and Abe, K.

Effects of doping elements on oxidation properties
of V-Cr-Ti type alloys in several environments

Journal of Nuclear Materials

307-311 (2002) 601-604

59

2002

Pint, B.A., DeVan, J.H. andDiStefano, J.R.

Temperature Limits on Compatibility of Insulating
Ceramics in Lithium

Journal of Nuclear Materials

307-311 (2002) 1344-50

60

2002

Suzuki, A., Koch, F., Maier, H.,
Nishimura, H., and Muroga, T.

Fabrication of ceramics coatings on NIFS-HEAT byarc-source plasma-assisted deposition method forfusion blanket application

Journal of Plasma Fusion Research
SERIES

61

2002

Sakurai, T., Yoneoka, T., Tanaka, S.,
Suzuki, A., Muroga, T.

Control of nitrogen concentration in liquid lithiumby hot trapping

Fusion Engineering and Design

61-62 (2002) 763-768

62

2002

Smith, D.L., Konys, J., Muroga T. and Development of coating for fusion power
Evitkhin, V.
applications

Journal of Nuclear Materials

307-311 (2002) 1314-1322

63

2002

Sakurai, T. Yoneoka, T., Tanaka, S.,
Suzuki, A. and Muroga, T.

Control of the nitrogen concentration in liquid
lithium by the hot trap method

Journal of Nuclear Materials

307-311 (2002) 1380-1384

64

2003

Pint, B.A., DiStefano J.R. andTortorelli, P.F.

High Temperature Compatibility Issues for Fusion
Reactor Structural Materials

Fusion Science and Technology

44 (2003) 433-40

65

2003

Suzuki, A., Muroga, T., Pint, B.A.,
Yoneoka, T., Tanaka, S.

Corrosion behaviour of AlN for self-cooled Li/V
blanket application

Fusion Engineering and Design

69 (2003) 397-401

66

2004

Pint, B.A., Tortorelli, P.F., Jankowski,
Recent progress in the development of electricallyA.,J. Hayes, J., Muroga, T., Suzuki,A.,
insulating coatings for a liquid lithium blanket
Yeliseyeva. O.I., and Chernov, V.M.

Journal of Nuclear Materials

329-333 (2004) 119-124

67

2004

Tanaka, T., Suzuki, A., Muroga, T.,
Sato, F., Iida T. and Nishitani T.

Radiation induced conductivity of ceramic coating
materials under 14 MeV neutron irradiation

Journal of Nuclear Materials

329-333 (2004) 1434-1437

68

2004

Yao, Z., Suzuki, A., Muroga T. andKatahira, K.

Chemical formation of erbium oxide layer on V–4Cr–
4Ti during exposure to liquid lithium doped with
Journal of Nuclear Materials
erbium329-333䠄2004䠅1414-1418

69

2005

Pint, B.A., More, K.L., Meyer, H.M.
and DiStefano, J.R.

Recent Progress Addressing Compatibility Issues
Relevant to Fusion Environments

Fusion Science and Technology

47 (2005) 851-855

70

2005

Suzuki, A., Muroga, T., Yoneoka, T.,
Tanaka, S.

Compatibility of compound oxides with liquid
lithium for fusion reactor blanket application

Journal of Physics and Chemistryof Solids

66 (2005) 690-693

A−70

5 (2002) 551-555

71

2005

Tanaka, T., Shikama, T., Narui, M.,
Tsuchiya, B., Suzuki A. and Muroga
T.

Evaluation of insulating property of ceramicmaterials for V/Li blanket system under fission
reactor irradiation

Fusion Engineering and Design

75-79 (2005) 933-937

72

2005

Sawada, A., Suzuki, A., Maier, H.,
Koch, F., Terai T. and Muroga T.

Fabrication of yttrium oxide and erbium oxide
coatings by PVD methods

Fusion Engineering and Design

75-79 (2005) 737-740

73

2005

Yao, Z., Suzuki, A., Muroga, T.,
Katahira, K.

In situ formation and chemical stability of Er2O3
coating on V-4Cr-4Ti in liquid lithium

Fusion Engineering and Design

75-79 (2005) 1015-1019

74

2006

Nagasaka, T., Muroga, T., Li, M.,
Tensile property of low activation vanadium alloy
Hoelzer, D.T., Zinkle, S.J., Grossbeck,
after liquid lithium exposure
M.L., and Matsui, H.

Fusion Engineering and Design

81 (2006) 307-313

75

2006

Jankowski, A. F., Saw, C. K., Ferreira,Morphology, Microstructure and Residual Stress in
J. L., Harper, J. S., Hayes J. P. and
EB-PVD Erbia Coatings
Pint, B. A.

Journal of Materials Science42 (2006) 5722-5727

76

2006

Pint, B. A., Moser, J. L. andTortorelli, P. F.

Liquid Metal Compatibility Issues for Test Blanket
Modules

Fusion Engineering and Design

81 (2006) 901-908

77

2006

Yao, Z., Suzuki, A., Muroga T. andNagasaka T.

Structural stability and self-healing capability of
Er2O3 in situ coating on V–4Cr–4Ti in liquid lithium

Fusion Engineering and Design

81 (2006) 2887-2892

78

2006

Tanaka, T., Nagayasu, R., Sato, F.,
Muroga, T., Ikeda, T. and Iida, T.

Comparison of electrical properties of ceramic
insulators under gamma ray and ion irradiation

Fusion Engineering and Design81(2006) 1027-1031

79

2006

Yao, Z., Suzuki, A., Muroga, T.,
Yeliseyeva O. and Nagasaka, T.

The in situ growth of Er2O3 coatings on V–4Cr–4Ti in
Fusion Engineering and Design
liquid lithium

81(2006) 951-956

2007

Muroga, L., Chen, J.M., Chernov,
V.M., Fukumoto, K., Hoelzer, D.T.,
Review of advances in development of vanadium
Kurtz, R.J., Nagasaka, T., Pint, B.A.,
alloys and MHD insulator coatings
Satou, M., Suzuki A., and Watanabe,
H.

Journal of Nuclear Materials

367-370 (2007) 780-787

81

2007

Li, M, Nagasaka, T, Hoelzer, DT,
Grossbeck, ML, Zinkle, SJ, Muroga,
T, Fukumoto, K, Matsui, H, andNarui, M

Biaxial thermal creep of two heats of V-4Cr-4Ti at
700 and 800 °C in a liquid lithium environment

Journal of Nuclear Materials

367-370 (2007) 788-793

82

2007

Pint, B. A., Moser, J. L., Jankowski, A. Compatibility of Multi-Layer, Electrically Insulatingand Hayes, J.
Coatings For the Vanadium-Lithium Blanket

Journal of Nuclear Materials

367-370 (2007) 1165-1169

83

2007

Nagura, M., Kondoh, M., Suzuki, A., Experimental Study on Corrosion of Ceramic
Muroga T., and Terai, T.
materials in National Convection Lithium Loop

Fusion Science and Technology

52 (2007) 625-629

84

2007

Tanaka, T., Nagayasu, R., Sawada,
A., Ikeda, T., Sato, F., Suzuki, A.,
Muroga T. and Iida T.

Journal of Nuclear Materials

367-370 (2007) 1155-1159

2009

Pint, B. A., Pawel, S. J., Howell, M.,
Moser, J. L., Garner, G. W., Santella, Initial Characterization of V-4Cr-4Ti and MHD
M. L., Tortorelli, P. F., Wiffen, F. W. Coatings Exposed to Flowing Li,
and DiStefano, J. R.

Journal of Nuclear Materials

386-388, 30 (2009) 712-715

Fusion Engineering and Design

61-62 (2002) 757-762

8085Electrical insulating property of ceramic coating
materials in radiation and high-temperatureenvironment

Task12BVanadiumAlloyCapsuleIrradiation
86

2002

Nagasaka, T., Heo, N. J., Muroga T.,
and Imamura, M.

Examination of fabrication process parameters for
improvement of low-activation vanadium alloys

87

2002

Heo, N. J., Nagasaka, T. ,Muroga, T.,
Metallurgical and mechanical properties of laser
Nishimura, A., Shinozaki K., andweldment for low activation V-4Cr-4Ti alloy
Takeshita, N.

Fusion Engineering and Design

61-62 (2002) 749-755

88

2002

Nishimura, A., Nagasaka T., andMuroga, T.

Journal of Nuclear Materials

307-311 (2002) 571-575

89

2002

Watanabe, H., Suda, M., Muroga, T., Oxide formation of a purified V-4Cr-4Ti alloy during
and Yoshida, N.
heat treatment and ion irradiation

Journal of Nuclear Materials

307-311 (2002) 408-412

90

2002

Grossbeck, M. L., King, J. F.,
Nagasaka T., and David, S. A.

Journal of Nuclear Materials

307-311 (2002) 1590-1594

Fracture toughness of high-purity V-4Cr-4Ti alloy(NIFS-HEAT-2) at room temperature

Gas tungsten arc welding of vanadium alloys with
impurity control

A−71

91

2002

Heo, N. J., Nagasaka, T., Muroga, T., Effect of impurity levels on precipitation behavior in
Journal of Nuclear Materials
and Matsui, H.
the low-activation V-4Cr-4Ti alloys

307-311 (2002) 620-624

92

2002

Fabrication using a levitation melting method of VChuto, T., Satou, M., Hasegawa, A.,
4Cr-4Ti-Si-Al-Y alloys and their mechanicalAbe, K., Nagasaka T., and Muroga, T.
properties

Journal of Nuclear Materials

307-311 (2002) 555-559

93

2002

Effects of post-weld heat treatment conditions on
Nagasaka, T., Muroga, T., Grossbeck,hardness, microstructures and impact properties of
M. L., and Yamamoto, T.
vanadium alloys

Journal of Nuclear Materials

307-311 (2002) 1595-1599

94

2002

Nagasaka, T., Muroga, T.,, Wu, W.C., Low Activation Characteristics of Several Heats of V- Journal of Plasma and Fusion
Xu, Z.Y., and Imamura, M.
4Cr-4Ti Ingot
Research SERIES

5 (2002) 545-550

95

2002

Gelles, DS

Microstructural examination of irradiated andunirradiated V-4Cr-4Ti pressurized creep tubes

Journal of Nuclear Materials

307-311 (2002) 393-397

96

2002

Toloczko, MB, Kurtz, RJ, Hasegawa,A, and Abe, K

Shear punch tests performed using a new low
compliance test fixture

Journal of Nuclear Materials

307-311 (2002) 1619-1623

97

2002

Hoelzer, DT and Rowcliffe, AF

Investigating solute interactions in V-4Cr-4Ti basedon tensile deformation behavior of vanadium

Journal of Nuclear Materials

307-311 (2002) 596-600

98

2002

Odette, GR, He, MY, Donahue, EG,
Spatig, P, and Yamamoto, T.

Modeling the multiscale mechanics of flow
localization-ductility loss in irradiation damaged bcc Journal of Nuclear Materials
alloys307-311 (2002) 171-178

99

2002

Lucas, GE, Odette, GR, Sokolov, M,
Spatig, P, Yamamoto, T, Jung, P

Recent progress in small specimen test technology

Journal of Nuclear Materials

307-311 (2002) 1600-1608

100

2002

Odette, GR, He, M, Gragg, D,
Klingensmith, D, Lucas, GE

Some recent innovations in small specimen testing

Journal of Nuclear Materials

307-311 (2002) 1643-1648

101

2002

Zinkle, SJ, Hashimoto, N, Hoelzer,
DT, Qualls, AL, Muroga, T, andSingh, BN

Effect of periodic temperature variations on the
microstructure of neutron-irradiated metals

Journal of Nuclear Materials

307-311 (2002) 192-196

102

2003

Nagasaka, T., Muroga, T., andIikubo, T.

Development of tubing technique for high-purity
low activation vanadium alloys

Fusion Science and Technology

44 (2003) 465-469

103

2003

Heo, N., Nagasaka, T., Muroga, T.,
Nishimura, A., Shinozaki, K.,
Watanabe, H.

Mechanical properties of laser weldment of V-4Cr4Ti alloy

Fusion Science and Technology

44 (2003) 470-474

104

2004

Fukumoto, K., Matsui, H., Narui, M., Manufacturing pressurized creep tubes from highly
Nagasaka, T., Muroga, T.
purified V-4Cr-4Ti alloys, NIFS-Heat2

Journal of Nuclear Materials

335 (2004) 103-107

105

2004

Koyama, M., Fukumoto, K., Matsui,
H.

Effects of purity on high temperature
mechanicalproperties of vanadium alloys

Journal of Nuclear Materials

329-333 (2004)
442-446

106

2004

Fukumoto, K., Matsui, H., Muroga,
T., Zinkle, S. J., Hoelzer, D. T.,
Snead, L. L.

Varying temperature effects on mechanicalproperties of vanadium alloys during neutron
irradiation

Journal of Nuclear Materials

329-333 (2004) 472-476

107

2004

Sugiyama, M., Fukumoto, K., Matsui, Dislocation channel formation process in V 䠉Cr䠉Ti
Journal of Nuclear Materials
H.
alloys irradiated below 300䜪C

329-333 (2004) 467-471

108

2004

Chuto, T., Satou, M., Hasegawa, A., Effects of small amount of additional elements on
Abe, K., Muroga T., and Yamamoto, control of interstitial impurities and mechanicalproperties of V-4Cr-4Ti-Si-Al-Y
N.

Journal of Nuclear Materials

109

2004

Chuto. T,, Satou, M., Hasegawa, A., Changes in mechanical properties of high-purity VAbe, K., Muroga, T., and Yamamoto, 4Cr-4Ti-Si, Al, Y alloys after neutron irradiation atN.
relatively low temperatures

ASTM Special TechnicalPublications STP

110

2004

Kurtz, R.J, Abe, K., Chernov, V.M.,
Hoelzer, D.T., Matsui, H., Muroga,T., and Odette, G.R.

111

2004

Watanabe, H., Nagamine M.,
Effects of Ion Irradiation on Yag Laser Welded V-4CrYamasaki, K., Yoshida, N., Nagasaka,
Journal of Plasma Fusion Res
4Ti AlloyT., Muroga, T., Shinozaki, K

80, No.10 (2004) 889-894

112

2005

Muroga, T., Nagasaka, T., Nishimura Improvement of Vanadium Alloys by Precipitate
Materials Science ForumA., and Chen, J.M.
Control for Structural Component of Fusion Reactors

475-479 (2005) 1449-1454

Recent progress on development of vanadium alloys
Journal of Nuclear Materials
for fusion

A−72

326 (2004) 1-8

1447 (2004) 693-701

329-333 (2004) 47-55

113

2005

Muroga, T.

Materials Transactions

46 (2005) 405-411

114

2005

Nagasaka, T. Muroga, T., Watanabe, Recovery of hardness, impact properties andH., Yamasaki, K., Heo, N-J., Shinozaki microstructure of neutron-irradiated weld joint of a Materials Transactions
K., and Narui M.
fusion candidate vanadium alloys

46 (2005) 498-502

115

2005

Nagasaka, T., Muroga, T., Noda, N.,
Kawamura M., and Ise, H.

Tungsten Coating on Low Activation Vanadium Alloy
Fusion Science and Technology
by Plasma Spray Process

47 (2005) 876-880

116

2005

Lee, CY, Donahue, EG, and Odette,GR, “,” Advances in Fracture andStrength, Pts 1-4, Key Engineering
Materials

Verification of mechanical properties of a V-4CR-4TI
Key Engineering Materials
alloy using finite element method

117

2005

Watanabe, H., Nagamine, M.,
The microstructure of laser welded V-4Cr-4Ti alloy
Yamasaki, A., Yoshida, N., Nagasaka,
after ion irradiationT., Muroga, T.

118

2005

Fukumoto, K., Takahashi, S., Kurtz,
R.J., Smith, D.L., and Matsui, H.

Microstructural examination of V-(Fe or Cr)-Ti alloys
Journal of Nuclear Materials
after thermal-creep or irradiation-creep tests

341 (2005) 83-89

119

2005

Fukumoto, K., Takahashi, K., Anma,Y., Matsui, H.

Effect of Impurities on Microstructural Evolution andMaterials Transactions
Deformation Process of Ion-Irradiated V-Cr-Ti alloys

46 (2005) 503-510

120

2005

Kurishita, H., Kuwabara, T.,
Hasegawa, M., Kobayashi, S., andNakai, K.

Microstructural control to improve the resistance to
Journal of Nuclear Materials
radiation embrittlement in vanadium

343 (2005) 318-32

121

2006

Nagasaka, T., Muroga, T., Li, M.,
Tensile property of low activation vanadium alloy
Hoelzer, D.T., Zinkle, S.J., Grossbeck,
after liquid lithium exposure
M.L., and Matsui, H.

Fusion Engineering and Design

122

2006

Nagasaka, T. Muroga, T., Fukumoto, Development of fabrication technology for low
K., Watanabe, H., Grossbeck, M.L., activation vanadium alloys as fusion blanket
structural materials
and Chen, J.M.

Nucl. Fusion

2007

Muroga, L., Chen, J.M., Chernov,
V.M., Fukumoto, K., Hoelzer, D.T.,
Review of advances in development of vanadium
Kurtz, R.J., Nagasaka, T., Pint, B.A.,
alloys and MHD insulator coatings
Satou, M., Suzuki A., and Watanabe,
H.

Journal of Nuclear Materials

367-370(2007)
780-787

124

2007

Li, M., Nagasaka, T., Hoelzer, D.T.,
Grossbeck, M.L., Zinkle, S.J.,
Muroga, T., Fukumoto, K., Matsui,H., and Narui, M.

Journal of Nuclear Materials

367-370 (2007) 788-793

125

2007

Fukumoto, K., Nagasaka, T., Muroga, Creep mechanism of highly purified V–4Cr–4Ti alloys
Journal of Nuclear Materials
T., Nita, N., Matsui, H.
during thermal creep in a vacuum367-370 (2007) 834-838

126

2007

Fukumoto, K., Sugiyama, M., Matsui, Features of dislocation channeling in neutronH.
irradiated V–(Fe, Cr)–Ti alloy

Journal of Nuclear Materials

367-370 (2007) 829-833

127

2007

Watanabe, H., Yamasaki, K.,
Higashizima, A., Yoshida, N.,
Nagasaka, T., Muroga, T.

The microstructure of laser welded V-4Cr-4Ti alloy
after neutron irradiation

Journal of Nuclear Materials

367-370 (2007) 794-799

128

2007

Rowcliffe, A.F., Hoelzer, D.T., Kurtz, Oxidation behavior of a V-4Cr-4Ti alloy during the
R.J., and Young, C.M.
commercial processing of thin-wall tubing

Journal of Nuclear Materials

367-370 (2007) 839-843

129

2007

Gelles, D.S., Toloczko, M.B., andKurtz, R.J.

Thermal creep mechanisms in V-4Cr-4Ti pressurized
Journal of Nuclear Materials
tube specimens

367-370 (2007) 869-875

130

2009

Li, M., Hoelzer, D.T., Grossbeck M.L.,
Rowcliffe, A.F., Zinkle, S.J., andIrradiation creep of the US Heat 832665 of V-4Cr-4Ti Journal of Nuclear Materials
Kurtz, R.J.

386-388 (2009) 618-621

131

2009

Muroga, T., Nagasaka, T., Li, Y., and Microstructure of Creep-deformed V-4Cr-4Ti
Chen, J.M.
Strengthened by Precipitation and Cold Rolling

Journal of Nuclear Materials

386-388 (2009) 606-609

132

2009

Watanabe, H., Higashizima. A.,
Yoshida, N., Nagasaka. T., Muroga,
T.

The Microstructure of Laser Welded Y Doped V-4CrJournal of Nuclear Materials
4Ti Alloys after Ion Irradiation

386-388 (2009) 598-601

123

Vanadium Alloys for Fusion Blanket Applications

Biaxial thermal creep of two heats of V-4Cr-4Ti at
700 and 800 °C in a liquid lithium environment

A−73

Materials Science Forum Volumes

297 - 300 (2005) 1013-1018

475-479 (2005) 1491-1496

81 (2006) 307-313

46 No 5 (2006) 618-625

133

2008

Watanabe, H., Yamasaki, M.,
The Effects of Postwelding Heat Treatment on
Higashizima. A., Yoshida, N.,
Microstructural Evolution of Yag Laser Welded VNagasaka, T., Muroga, T., Shinozaki,
4Cr-4Ti Alloy
K.

Journal of plasma and fusion
research

84(1) (2008) 46-50

Fusion Engineering and Design

81 (2006) 937-944

Journal of the American CeramicSociety88 (2005) 3088-3095

Task21SiC/SiCFundamentalsandMaterialProcessing
134

2006

Y. Katoh, T. Nozawa, L.L. Snead, T.
Hinoki and A. Kohyama

Property tailorability for advanced CVI siliconcarbide composites for fusion

135

2005

Mechanical properties of thin pyrolitic carbon
Katoh, Y., Nozawa, T., Snead, L.L., , J.
interphase SiC-Matrix composites reinforced with
Am. Ceram. Soc.
near-stoichiometric SiC fibers

136

2005

Katoh Y., Snead, L.L., Nozawa, T.,
Hinoki, T., Kohyama, A., Igawa, N.,
Taguchi, T.

Mechanical properties of chemically vaporinfiltrated silicon carbide structural composites with
Mater. Trans.
thin carbon interphases for fusion and advanced
fission applications

46 (2005) 527-535

137

2005

Nozawa, T., Katoh, Y., Kohyama, A

Evaluation of tensile properties of SiC/SiC
composites with miniaturized specimens

Mater. Trans46 (2005) 543-551

138

2005

Igawa, N., Taguchi, T., Nozawa, T.,
Snead, L.L., Hinoki, T., McLaughl,
J.C., Katoh, Y., Jitsukawa, S.,
Kohyama

Fabrication of SiC fiber reinforced SiC composite bychemical vapor infiltration for excellent mechanicalproperties

Journal of Physics and Chemistryof Solids

66 (2005) 551-554

139

2005

Nozawa, T., Katoh, Y., Snead, L.L.,
Hinoki, T., Kohyama, A.

Tensile and thermal properties of chemically vaporinfiltrated silicon carbide composites with various
Ceram. Eng. and Sci. Proc.
high-modulus fiber reinforcements

26 (2005) 311-318

140

2005

Katoh, Y., Nozawa, T., Kotani, M.,
Ozawa, K., Kohyama, A

Microstructures and flexural properties of hightemperature-pyrolyzed PIP-SiC/SiC composites

Key Eng. Mater.

287 (2005) 346-351

141

2004

Taguchi, T., Nozawa, T., Igawa, N.,
Katoh, Y., Jitsukawa, S., Kohyama,A., Hinoki, T., Snead, L.L.

Fabrication of advanced SiC fiber/F-CVI SiC matrix
composites with SiC/C multi-layer interphase

J. Nucl. Mater.

329-33 (2004) 572-576

142

2004

Nozawa, T., Ozawa, K., Katoh, Y.,
Kohyama, A.

Effect of heat treatment on microstructure andmechanical properties of stoichiometric SiC/SiC
composites

Mater. Trans45 (2004) 307-310

143

2004

Katoh, Y., Lowden, R.A., Yang, W.,
Nozawa, T., Hinoki, T., Kohyama, A.

Fast Fracture Properties of Thin Interphase Silicon
Carbide Composites, in: M. Singh, R.J. Kerans, E.
Lara-Curzio, R. Naslain (Eds.), High Temperature
Ceramic Matrix Composites 5

The American Ceramic Society,
Westerville, OH(2004) 169-174

144

2004

Y. Katoh, A. Kohyama, T. Nozawa
and M. Sato

SiC/SiC composites through transient eutectic-phase
Journal of Nuclear Materials
route for fusion applications

329-333, Part 1 (2004) 587-591

145

2004

S.J. Son, K.H. Park, Y. Katoh and A.
KohyamaInterfacial reactions and mechanical properties of W
Journal of Nuclear Materials–SiC in-situ joints for plasma facing components

329-333, Part 2 (2004) 15491552

146

2003

Specimen Size Effect on the Tensile and Shear
Nozawa, T., Katoh, Y., Kohyama, A.,
Properties of the High-Crystalline and High-Dense
Lara-Curzi E.
SiC/SiC Composites

147

2003

Y. Katoh, A. Kohyama, T. Hinoki and Progress in SiC-Based Ceramic Composites for Fusion
Fusion Science and Technology
L.L. Snead
Applications

44 (2003) 155-162

148

2003

Effect of Carbon and Silicon Carbide/Carbon
W. Yang, A. Kohyama, Y.T. Katoh, H. Interlayers on the Mechanical Behavior of TyrannoAraki, J.N. Yu and T. Noda
SA-Fiber-Reinforced Silicon Carbide-Matrix
Composites

Journal of the American CeramicSociety86, 5 (2003) 851-856

149

2003

S.M. Dong, Y. Katoh and A. Kohyama

Processing optimization and mechanical evaluationof hot pressed 2D Tyranno-SA/SiC composites

Journal of the European CeramicSociety23 (2003) 1223-1231

150

2003

T. Hino, T. Jinushi, Y. Hirohata, M.
Hashiba, Y. Yamauchi, Y. Katoh and
A. Kohyama

Helium Gas Permeability of SiC/SiC Composite
Developed for Blanket Component

Fusion Science and Technology

43 (2003) 184-190

A−74

Ceram. Eng. and Sci. Proc.

24 (2003) 415-420

151

2003

J.S. Park, Y. Katoh and A. Kohyama

Measurements of continuous R-curve behavior inceramic matrix composites

Ceramic Engineering and Science
Proceedings

152

2002

Igawa, N., Taguchi, T., Snead, L.L.,
Katoh ,Y., Jitsukawa, S., Kohyama,A., McLaughl, J.C.

Optimizing the fabrication process for superiormechanical properties in the FCVISiC
matrix/stoichiometric SiC fiber composite system,

J. Nucl. Mater.

307 (2002) 1205-1209

153

2002

Nozawa, T., Katoh ,Y., Kohyama, A., Advances in Ceramic Matrix Composites VIII:
Lara-Curzi, E.
Ceramic Transactions

The American Ceramic Society,
Westerville, OH

139 (2002) 127-138

154

2002

Nozawa, T., Hinoki, T., Katoh, Y.,
Kohyama, A., Lara-Curzi, E.(Eds.)

Specimen Size Effects on the Tensile Properties of
2D/3D SiC/SiC Composites

ASTM International, WestConshohocken, PA

2002

155

2002

W. Yang, A. Kohyama, T. Noda, Y.
Katoh, T. Hinoki, H. Araki and J. Yu

Interfacial characterization of CVI-SiC/SiC
composites

Journal of Nuclear Materials

307-311, Part 2 (2002)
1088-1092

156

2002

K. Hironaka, T. Nozawa, T. Hinoki, N.
High-temperature tensile strength of nearIgawa, Y. Katoh, L.L. Snead and A.
stoichiometric SiC/SiC composites
Kohyama

Journal of Nuclear Materials

307-311, Part 2 (2002)
1093-1097

157

2002

Y. Hirohata, T. Jinushi, Y. Yamauchi,
Gas permeability of SiC/SiC composites as fusion
M. Hashiba, T. Hino, Y. Katoh and A.
reactor material
Kohyama

Fusion Engineering and Design

61-62 (2002) 699-704

158

2002

Thermo-mechanical properties and microstructure
Y. Katoh, S.M. Dong and A. Kohyama of silicon carbide composites fabricated by nanoinfiltrated transient eutectoid process

Fusion Engineering and Design

61-62 (2002) 723-731

159

2002

J.S. Park, Y. Katoh, A. Kohyama, S.P. Evaluation of fracture toughness of ceramic matrix
Lee and H.K. Yoon
composites using small specimens

Fusion Engineering and Design

61-62 (2002) 733-738

160

2002

Effects of Interlayers on InterfacialShear Strength
W. Yang, H. Araki, T. Noda, Q. Hu, H.
and Flexural Properties of Tyranno-SA FiberSuzuki, Y. Katoh and A. Kohyama
Reinforced CVI-SiC/SiC Composites

Ceramic Transactions

144 (2002) 273-280

161

2002

J.S. Park, Y. Katoh, A. Kohyama and
H.K. Yoon

Ceramic Transactions

144 (2002) 263-272

162

2002

T. Nozawa, K. Hironaka, Y. Katoh, A. Tensile Strength of Chemical Vapor Infiltrated
Adavanced SiC Fiber Composites at ElevatedKohyama, T. Taguchi, S. Jitsukawa
Temperaturesand L.L. Snead

Ceramic Transactions

144 (2002) 245-252

163

2002

A Novel Processing Technique of Silicon CarbideY. Katoh, S.M. Dong and A. Kohyama Based Ceramic Composites for High Temparature
Applications

Ceramic Transactions

144 (2002) 77-86

164

2002

T. Taguchi, N. Igawa, S. Jitsukawa, T. Opimizing the Fabrication process for excellent
Nozawa, Y. Katoh, A. Kohyama, L.L. mechanical properties in Stoichiometric SiC Fiber /FCVI SiC Matrix Composites
Snead and J.C. McLaughlin

Ceramic Transactions

144 (2002) 69-76

165

2002

T. Hinoki, L.L. Snead, T. Taguchi, N.
Optimization and Characterization of Chemical
Igawa, W. Yang, T. Nozawa, Y. Katoh
Vapor Infiltrated SiC/SiC Composites
and A. Kohyama

Ceramic Transactions

144 (2002) 55-67

166

167

168

Fracture Resistance Evaluation of Ceramic Matrix
Composities

24 (2003) 421-426

26th Annual Conference on
Preliminary Study of Influence of Test Specimen Size Composites, Advanced Ceramics,
on the Fracture Behaviour of 2D Woven CeramicMaterials, and Structures: A:
Matrix Composies
Ceramic Engineering and Science
Proceedings

23, 3 (2002) 469-475

2002

J.S. Park, Y. Katoh and A. Kohyama

2002

K. Hironaka, T. Nozawa, T. Hinoki, Y. High Temperature Tensile Properties of NearKatoh, A. Kohyama, T. Taguchi, N.
Stoichiometric Sic Fiber-Reinforced Sic Matrix
Igawa and L.L. Snead
Composties

26th Annual Conference on
Composites, Advanced Ceramics,
Materials, and Structures: A:
Ceramic Engineering and Science
Proceedings

23, 3 (2002) 403-409

Y. Katoh, A. Kohyama, S.M. Dong, T. Microstructure and Properties of Liquid Phase
Hinoki and J.J. Kai
Sintered SiC/SiC Composites

26th Annual Conference on
Composites, Advanced Ceramics,
Materials, and Structures: A:
Ceramic Engineering and Science
Proceedings

23, 3 (2002) 362-370

2002

Task22SiCSystemThermomechanics
169

2004

Ying, A., Yokomine, T. Shimizu, A.,
Abdou, M., Kohyama, A.

Impact of Material System Thermomechanics
Performance on He-Cooled Ceramic Breeder Blanket Journal of Nuclear Materials
Designs with SiCf/Sic

A−75

329-333, Part 2 (August 2004)
1605 - 1609

170

2004

G. R. Longhurst, L. L. Snead, A.
Abou-Sena

The Status of Beryllium Research for Fusion in the
United States

Proceedings of the 6th IEAInternational Workshop on
Beryllium Technology for Fusion,
Miyazaki, Japan, March 2004

171

2005

An, Z., Ying, A., Abdou, M.

Experimental and numerical study of ceramic
breeder pebble bed thermal deformation behavior

Fusion Science &TechnologyFusion Science &Technology

47 (4) (May 2005)
1101 - 1105

172

2005

Abou-Sena, A., Ying, A., Abdou, M.

Effective thermal conductivity of lithium ceramic
pebble beds for fusion blankets: a review

Fusion Science & Technology

47 (4) (May 2005)
1094 - 1100

173

2005

Z. An, A. Ying, M. Abdou

Proc. 2005 Joint ASME/ASCE/SES
Experimental and numerical study on the
Conference on Mechanics andthermomechanical properties of ceramic pebble bed
Materials (McMat2005), Baton
structure
Rouge, LA (06/01/2005)

174

2005

Z. An, A. Ying and M. Abdou

Thermo-mechanical analysis of ITER test unit cellunder pulse operation

175

2006

Ali Abou-Sena, Alice Ying,
Mohamed Abdou

Experimental Measurements of the Effective
Journal of Materials Processing
Thermal Conductivity of a Lithium Titanate (Li2TiO3)
Technology
Pebbles-Packed Beds

176

2006

Experimental Study of the Interaction of Ceramic
Calderoni, P., Ying, A., Sketchley, T.,
Breeder Pebble Beds with Structural Materials
Abdou, M.
under Thermo-Mechanical Loads

177

An, Z., Ying, A., Abdou, M.

Numerical characterization of thermo-mechanicalperformance of breeder pebble beds

Proceedings of 21st IEEE/NPSS
Symposium on Fusion Engineering
2005, Oct. 2005

Fusion Engineering & Design

181 (January 2006)
206-21281 (1-7) (February 2006)
607 - 612

Proceedings of the 12th
International Conference on
Fusion Reactor Materials (ICFRM12), to be published in Journal of
Nuclear Materials (2006)

Task23SiCCapsuleIrradiation
178

2002

Hinoki, T., Snead, L.L., Katoh, Y.,
The effect of high dose/high temperature irradiation
Hasegawa, A., Nozawa, T., Kohyama, on high purity fibers and their silicon carbide
J. Nucl. Mater.
A
composites

179

2002

Nozawa, T., Hinoki, T., Katoh, Y.,
Kohyama, A.

Effects of fibers and fabrication processes onmechanical properties of neutron irradiated SiC/SiC
composites

Journal of Nuclear Materials

180

2002

Hinoki, T., Katoh, Y., Kohyama, A.

Effect of fiber properties on neutron irradiated
SiC/SiC composites

Mater. Trans

181

2002

H. Kishimoto, Y. Katoh and A.
Kohyama

Microstructural stability of SiC and SiC/SiC
composites under high temperature irradiation
environment

Journal of Nuclear Materials

307-311, Part 2 (2002)
1130-1134

182

2002

K.H. Park, Y. Katoh, H. Kishimoto and Evaluation of dual-ion irradiated β-SiC by means of
A. Kohyama
indentation methods

Journal of Nuclear Materials

307-311, Part 2 (2002)
1187-1190

183

2002

Y. Katoh, H. Kishimoto and A.
Kohyama

The influences of irradiation temperature andhelium production on the dimensional stability ofsilicon carbide

Journal of Nuclear Materials

307-311, Part 2 (2002)
1221-1226

184

2002

Y. Katoh, H. Kishimoto and A.
KohyamaLow Temperature Swelling in Beta-SiC Associatedwith Point Defect Accumulation

Materials Transactions

185

2002

S. Nogamia, A. Hasegawa, L. L.
Snead

Indentation fracture toughness of neutron
irradiated silicon carbide

Journal of Nuclear Materials

307-311, Part 2 (2002)
1163-1167

186

2002

A. Hasegawa , S. Nogami, T. Aizawa, Mechanical property change and swelling behavior
K. Katou and K. Abeof SiC fiber after light-ion irradiation

Journal of Nuclear Materials

307-311, Part 2 (2002)
1152-1156

187

2002

S. Nogami , S. Ohtsuka, M. B.
Toloczko, A. Hasegawa and K. Abe

Analysis of possible deformation mechanisms inhelium–ion irradiated SiC

Journal of Nuclear Materials

307-311, Part 2 (2002)
1178-1182

188

2003

Radiation and helium effects on microstructures,
Y. Katoh, M. Ando and A. Kohyama nano-indentation properties and deformation
behavior in ferrous alloys

Journal of Nuclear Materials

323, Issues 2-3, (2003)
251-262

A−76

307 (2002) 1157-116

307 (2002) 1173-1177

43 (2002) 617-621

43 (2002) 612-616

189

2003

K.H. Park, S. Kondo, Y. Katoh and A. Mechanical Properties of -SiC After Si- and Dual Si +Kohyama
He-Ion Irradiation at Various Temperatures

Fusion Science and Technology

44 (2003) 455-459

190

2003

S. Kondo, K.H. Park, Y. Katoh and A. High Temperature Ion-Irradiation Effects on
Kohyama
Microstructural Evolution inβ -SiC

Fusion Science and Technology

44 (2003) 181-185

191

2003

A.Hasegawa, S.Nogami, S.Miwa,
K.Abe, T.Taguchi, N.Igawa

Synergistic Effect of Displacement Damage, Heliumand Hydrogen of Silicon Carbide Composite

Fusion Science and Technology

44 (1) (2003) 175-180

192

2004

Nogami, S., Hasegawa, Snead, L.L.,
Jones, R.H. Abe, K.

Effect of He pre-implantation and neutron
irradiation on mechanical properties of SiC/SiC
composite

Journal of Nuclear Materials

329–333 (2004) 577–581

193

2004

Nozawa, T., Hinoki, T., Snead, L.L.,
Katoh, Y., Kohyama, A.

Neutron irradiation effects on high-crystallinity andnear-stoichiometry SiC fibers and their composites

Journal of Nuclear Materials

329-33 (2004) 544-548

194

2004

Mechanical and Structural Property Change ofNogami, S., Miwa, M., Hasegawa, A., Monolithic SiC and Advanced SiC/SiC Composites
Abe, K.
due to Low Temperature He+-ion Irradiation andPost-irradiation High Temperature Annealing

American Society for Testing andMaterials (ASTM) STP 1447

1447 (2004) 655-669

195

2004

Hasegawa, A., Miwa, S., Nogami,S., Taniguchi, A., Taguchi, T.,
Abe,K.

Journal of Nuclear Materials

329-333 (2004) 582-586

196

2005

Cavity Formation in a SiC/SiC Composites underMiwa, S., Hasegawa, A., Taguchi,T.,
Simutaneous Irradiation of Hydrogen, Helium andIgawa, N., Abe, K.
Silicon Ions

Materials Transactions

46(3) (2005) 536-542

197

2005

Nozawa, T., Ozawa, K., Kondo, S.,
Hinoki, T., Katoh, Y., Snead, L.L.,
Kohyama, A., Tensile

Flexural, and Shear Properties of Neutron Irradiated
SiC/SiC Composites with Different Fiber-Matrix
J. ASTM Int.
Interfaces

198

2005

Katoh, Y., Snead, L.L.

Bend stress relaxation creep of CVD silicon carbide

199

2005

Katoh, Y., Snead, L.L.

Mechanical Properties of Cubic Silicon Carbide after
J. ASTM Int. 2
Neutron Irradiation at Elevated Temperatures

200

2005

Kondo, S., Katoh, Y., Kishimoto, H.,
Hinoki, T., Kohyama, A.

Swelling and Recovery Behavior in Silicon Carbide
Irradiated at High Temperature

Proceedings of 2005 International
Congress on Advances in Nuclear
Power Plants (ICAPP-05),2005

2782-2787

201

2005

T. Hinoki and A. Kohyama

Current status of SiC/SiC composites for nuclear
applications

Annales de chimie science des matériaux30[6] (2005) 659-671

202

2005

A. Kohyama

Current Status of Fusion Reactor Structural
Materials R&D

Materials Transactions

46[3] (2005) 384-393

203

2005

A. Kohyama, K. Abe, A. Kimura, T.
Muroga and S. Jitsukawa

Recent Accomplishments and Future Prospects ofMaterials R&D in Japan

Fusion Science and Technology

47[4] (2005) 836-843

204

2005

K. Ozawa, S. Kondo, T. Hinoki, K.
Jimbo and A. Kohyama

Cavity Swelling Behavior in SiC/SiC Under Charged
Particle Irradiation

Fusion Science and Technology

47[4] (2005) 871-75

205

2005

H. Kishimoto, K. Ozawa, S. Kondo
and A. Kohyama

Effects of Dual-Ion Irradiation on the Swelling of
SiC/SiC Composites

Materials Transactions

206

2005

Dimension stability analysis of nite sic/sic composite
H. Kishimoto, T. Hinoki, K. Ozawa,
Ceramic Engineering and Science
using ion bombardments for the investigation of
K.-H. Park, S. Kondo and A. Kohyama
Proceedings
reliability as fusion materials

26[8] (2005) 215-222

207

2006

Katoh, Y., Nozawa, T., Snead, L.L.,
Hinoki, T., Kohyama, A.

81 (2006) 937-944

208

2006

Katoh, Y., Hashimoto, N., Kondo, S., Microstructural Development in Cubic Silicon
Journal of Nuclear Materials
Snead, L.L., Kohyama, A.
Carbide during Irradiation at Elevated Temperatures351 (2006) 228-240

209

2006

Ozawa, K., Hinoki, T., Nozawa, T.,
Evaluation of Fiber/Matrix Interfacial Strength of
Katoh, Y., Maki, Y., Kondo, S., Ikeda, Neutron Irradiated SiC/SiC Composites Using
S., Kohyama, A.
Hysteresis Loop Analysis of Tensile Test

Mater. Trans.

47 (2006) 207-210

210

2006

Katoh, Y., Snead, L.L., Nozawa, T.,
Windes, W.E., Morley N.B.

Advanced Radiation-Resistant Ceramic Composites

Advances in Science andTechnology

45 (2006) 1915-1924

211

2006

Y. Katoh, N. Hashimoto, S. Kondo,
L.L. Snead and A. Kohyama

Microstructural development in cubic silicon carbide
Journal of Nuclear Materials
during irradiation at elevated temperatures

Study of hydrogen effects on microstructuraldevelopment of SiC base䚷materials undersimultaneous irradiation with He- and Si-ion
irradiation conditions

Property tailorability for advanced CVI siliconcarbide composites for fusion

A−77

Ceram. Eng. and Sci. Proc.

Fusion Eng. and Design

2 (2005) 12884-12881-12813

26 (2005) 265-272(2005) 12377-12371-12313

46 [8] (2005) 1923-1927

351, Issues 1-3 (2006)
228-240

212

2006

K. Ozawa, T. Nozawa, T. Hinoki and
A. Kohyama

The effects of irradiation-induced swelling of
constituents on mechanical properties of advanced
SiC/siC composites

Ceramic Engineering and Science
Proceedings

27 (5) (2006) 157-167

213

2009

Nogami, S., Murayama, T., Nagata,Y., Hasegawa A.

Compatibility between SiC and Li Ceramics for Solid
Breeding Blanket System

Journal of Nuclear Materials

386-388 (2009) 628-630

214

2008

Nogami, S., Otake, N., Hasegawa,
A., Katoh, Y., Yoshikawa, A., Satou,
M., Oya, Y., Okuno, K.

Oxidation behavior of SiC/SiC composites for helium
Fusion Engineering and Design
cooled solid breeder

83, Issues 10-12 (2008)
1490-1494

215

2007

Nozawa, T., Katoh, Y., Snead, L.L.

The Effect of Neutron Irradiation on Interfacial Shear
Properties of Multilayered Interphase SiC/SiC
Journal of Nuclear Materials
Composite

3670-370 (2007) 685-691

216

2007

Katoh, Y., Nozawa, T., Snead, L.L.,
Hinoki, T.

Effect of Neutron Irradiation on Tensile Properties of
Journal of Nuclear Materials
Unidirectional Silicon Carbide Composites

367-370 (2007) 774-779

217

2007

Katoh, Y., Snead, L.L., Hinoki, T.,
Kondo, S., Kohyama, A

Irradiation Creep of Chemically Vapor Deposited
Silicon Carbide as Estimated by Bend Stress
Relaxation Method

Journal of Nuclear Materials

367-370 (2007) 758-763

218

2007

Ozawa, K., Nozawa, T., Katoh, Y.,
Hinoki, T., Kohyama, A.

Mechanical Properties and Microstructure ofAdvanced SiC/SiC composites after Neutron
Irradiation

Journal of Nuclear Materials

367-370 (2007) 713-718

219

2007

Katoh, Y., Snead, L.L., Henager, C.H.,
Current status and critical issues for development of
Journal of Nuclear Materials
Hasegawa, A., Kohyama, A.,
SiC composites for fusion applications
Riccardi, B., Hegema, J.B.J.

367-370 (2007) 659-671

Kondo, S., Katoh, Y., Kohyama, A.

Stoichiometric constraint for dislocation loop
growth in silicon carbide

Ceram. Eng. and Sci. Proc.

submitted (2007)

Nozawa, T., Katoh, Y., Snead, L.L.

The Effects of Neutron Irradiation on the Interfacial
Shear Strength of SiC/SiC Composites

Journal of Nuclear Materials

367-370, Part 1 (2007) 685-691

Mass-Transport Properties to Estimate Rates of
Tritium Recovery from Flibe Blanket

220

221

2007

Task31DesignbasedIntegrationModeling
222

2002

Fukada, S., Nishikawa, M., Sagara,A., Terai, T.

Fusion Science & Technology

41 (2002) 1054-1058

223

2002

Hashizume, H., Usui, Y., Kitajima, S., Numerical analysis of MHD flow in remountable first
Fusion Engineering and Design
Hida, T., Sagara, A.
wall

61-62 (2002) 251-254

224

2002

Toda, S., Chiba, S., Yuki, K., Omae,
M., Sagara, A.

Experimantal research on molten salt thermofluid
technology using a high-temperature molten salt
loop applied for a fusion reactor Flibe blanket

Fusion Engineering and Design63-64 (2002) 405-409

225

2003

Kunugi, T., Matsumoto, Y., Sagara,
A.

A new cooling concept of free surface flow balanced
Fusion Engineering and Design
with surface tension for FFHR

65 (2003) 381-385

226

2004

Hashizume, H., Usui, Y., Kitajima, S., New concept of the first wall to reduce MHD
Sagara, A.
pressure drop

International Journal of Applied
Electromagnetics and Mechanics

227

2005

Sagara, A., Imagawa, S., Mitarai, O.,
Dolan, T., Tanaka, T., Kubota, Y.,
Yamazaki, K., Watanabe, K.Y.,
Improved structure and long-life blanket concepts
Mizuguchi, N., Muroga, T., Noda, N.,
for heliotron reactors
Kaneko, O., Yamada, H., Ohyabu, N.,
Uda, T., Komori, A., Sudo, S., andMotojima, O.

Nuclear Fusion

45 (2005) 258-263

228

2005

Sagara, A., Tanaka, T., Muroga, T.,
Hashizume, H., Kunugi, T., Fukada,S., Shimizu, A.

Innovative Liquid Breeder Blanket Design Activities
in Japan

Fusion Science and Technology

47 (2005) 524-529

229

2005

Okumura, M., Yuki, K., Hashizume,
H., Sagara, A.

Evaluation of Flow Structure in Packed-Bed Tube by
Fusion Science and Technology
Visualization Experiment

47 (2005) 1089-1093

230

2005

Chiba, S., Omae, M., Yuki, K.,
Hashizume, H., Toda, S., Sagara, A.

Experimental Research on Heat Transfer
Enhancement for High Prandtl-Number Fluid
Experimental Research on Heat Transfer
Enhancement for High Prandtl-Number Fluid

Fusion Science and Technology

47, No.4 (2005) 569-573

231

2005

Tanaka, T., Muroga, T., Sagara, A.

Tritium Self-Sufficiency and Neutron Shielding
Performance of Self-Cooled Liquid Blanket System
for Helical Reactor

Fusion Science and Technology

47 (2005) 530-534

232

2005

Fukada, S., Anderl, R.A., Sagara, A.,
Nishikawa, M.

Diffusion Coefficient of Tritium Through Molten Salt
Flibe and Rate of Tritium Leak from Fusion Reactor Fusion Science and Technology
System48 (2005) 666-669

A−78

19, No.1-4 (2004) 591-595

233

2006

Satake, S., Kunugi, T., Naito, N.,
Sagara, A.

Direct numerical simulation of MHD flow withelectrically conducting wall

Fusion Engineering and Design81(2006) 367-374

234

2006

Fukada, S., Morisaki, A., Sagara, A.,
Terai, T.

Control of tritium in FFHR-2 self-cooled Flibe blanket Fusion Engineering and Design

81 (2006) 477–483

235

2006

Chiba, S, Yuki, K., Hashizume, H.,
Toda, S., Sagara, A.

Numerical research on heat transfer enhancement
for high Prandtl-number fluid

Fusion Engineering and Design

81 (2006) 513-517

236

2006

Muroga, T., Tanaka, T., Sagara, A.

Blanket neutronics of Li/vanadium-alloy and
Flibe/vanadium-alloy systems for FFHR

Fusion Engineering and Design

81 (2006) 1203-1209

2006

Sagara, A., Imagawa, S., Tanaka, T.,
Muroga, T., Kubota, Y., Dolan, T.,
Hashizume, H., Kunugi, T., Fukada,S., Shimizu, A., Terai, T., Mitarai, O.

Carbon tiles as spectral-shifter for long-life liquidblanket in LHD-type reactor FFHR

Fusion Engineering and Design

81 (2006) 1299–1304

238

2006

Sagara, A., Mitarai, O., Imagawa, S.,
Morisaki, T., Tanaka, T., Mizuguchi,N., Dolan, T., Miyazawa, J.,
Takahata, K., Chikaraishi, H.,
Yamada, S., Seo, K., Sakamoto, R.,
Conceptual design activities and key issues on LHDMasuzaki, S., Muroga, T., Yamada,type reactor FFHR
H., Fukada, S., Hashizume, H.,
Yamazaki, K., Mito, T., Kaneko, O.,
Mutoh, T., Ohyabu, N., Noda, N.,
Komori, A., Sudo, S., Motojima, O.,
and FFHR design group

Fusion Engineering and Design

81 (2006) 2703–2712

239

2006

Tanaka, T., Sagara, A., Muroga, T.,
Youssef, M.Z.

Development of three-dimensional neutronics
calculation system for design studies on helical
reactor FFHR

Fusion Engineering and Design

81 (2006) 2761–2766

240

2008

Tanaka, T., Sagara, A., Muroga, T.,
Youssef, M.Z.

Neutronics Investigation of Advanced Self-Cooled
Liquid Blanket Systems in Helical Reactor

Nuclear Fusion

48, No. 3 (2008) 035005

241

2007

Muroga, T., Tanaka, T., Li, Z., Sagara,
Tritium control for Flibe/V-alloy blanket system
A., and Sze, D.K.

Fusion Science & Technology

52 (2007) 682-686

242

2007

Satoh, T., Yuki, K., Chiba, S.,
Hashizume, H., Sagara, A.

Heat Transfer Performance for High Prandtl andHigh Temperature Molten Salt Flow in SpherePacked Pipes

Fusion Science & Technology

52 (2007) 618-624

243

2007

Fukada, S., Katayama, K., Terai, T.,
Sagara, A.

Recovery of Tritium from Flibe Blanket in Fusion
ReactorFusion Science & Technology

52 (2007) 677-681

237

Task32MaterialsModeling

2001

Proc. Fourth Pacific Rim Int. Conf.
Morishita, K., Wirth, B.D., Diaz de la Effects of Helium on Radiation Damage Processes in on Advanced Materials andRubia, T., Kimura, A.
Iron
Processing (PRICM4), (The Japan
Institute of Metals, 2001)

1383-1386

245

2001

Morishita, K., Sugano, R., Iwakiri, H.,
Thermal helium desorption from α-Iron
Yoshida, N., Kimura, A.

Proc. Fourth Pacific Rim Int. Conf.
on Advanced Materials andProcessing (PRICM4), (The Japan
Institute of Metals, 2001)

1395-1398

246

2002

Sugano, R., Morishita, K., Iwakiri, H., Effects of dislocation on thermal helium desorption
Yoshida, N.
from iron and ferritic steel

Journal of Nuclear Materials

307-311 (2002) 941-945

247

2002

Iwakiri, H., Morishita, K., Yoshida, N.

Effects of helium bombardment on the deuterium
behavior in tungsten

Journal of Nuclear Materials

307-311 (2002) 135-138

248

2003

Morishita, K., Sugano, R., Wirth B.D.,
Thermal stability of helium-vacancy clusters in iron
Diaz de la Rubia, T.

249

2003

Morishita, K., Sugano, R., Wirth, B.D.

250

2003

251

252

244

Nuclear Instruments and Methods
in Physics Research Section B

202 (2003) 76-81

MD and KMC modeling of the formation andmigration of He-V clusters in Fe

Journal of Nuclear Materials

323 (2003) 243-250

Morishita, K., Sugano, R., Wirth,
B.D.

Thermal stability of helium-vacancy clusters andbubble formation

Fusion Science Technology

44 (2) (2003) 441-445

2003

Sugano, R., Morishita, K., Kimura, A

Helium accumulation behavior in iron based model
alloysFusion Science Technology

44 (2) (2003) 446-449

2004

Sugano, R., Morishita, K., Kimura, A., Microstructural evolution in Fe and Fe-Cr model
Iwakiri, H., Yoshida, N.
alloys after He+ ion irradiations

Journal of Nuclear Materials

329-333 (2004) 942-946

A−79

Atomistic Modeling of Helium Bubble Formation in
Fe during Irradiation

Conference proceedings of Second
International Conference on
Multiscale Materials Modeling(MMM-II), UCLA, Los Angeles, CA,
USA, 2004

525-527

253

2004

Morishita, K., Sugano, R.

254

2004

Calculation of electronic structure at bonding
Satou, M., Komatsu, N., Sawada, T.,interface between vanadium and oxide ceramics for Journal of Nuclear Materials
Abe, K.
insulator coating applications

255

2004

Satou, M., Abe, K., Kioussis, N.,
Ghoniem, N.

256

2005

Okita, T., Wolfer, W.G., Garner, F.A., Effects of titanium additions to austenitic ternary
Philosophical Magazine
Sekimura, N.
alloys on microstructural evolution and void swelling

257

2006

Morishita, K., Sugano, R.

Mechanism map for nucleation and growth ofhelium bubbles in metals

Journal of Nuclear Materials

353 (2006) 52-65

258

2007

Morishita, K., Sugano, R.

Modeling of Helium Bubble Migration in bcc Fe

Nuclear Instruments and Methods
in Physics Research Section B

255 (2007) 52-56

259

2007

Watanabe, Y., Iwakiri, H., Yoshida,N., Morishita, K., Kohyama, A.

Formation of interstitial loops in tungsten under
helium ion irradiation: Rate theory modeling andexperiment

Nuclear Instruments and Methods
in Physics Research Section B

255 (2007) 32-36

260

2007

Morishita, K.

Atomistic evaluation of the point defect capture
efficiency of He-V clusters in α-Fe

Nuclear Instruments and Methods
in Physics Research Section B

255 (2007) 41-46

261

2007

Morishita, K.

Nucleation path of helium bubbles in metals during
irradiation

Philosophical Magazine

87 (2007) 1139-1158

262

2009

Morishita, K., Watanabe, Y.,
Nucleation and growth of vacancy clusters in β-SiC
Kohyama, A., Heinisch, H.L., Gao, F. during irradiation

Journal of Nuclear Materials

386-388 (2009) 30-32

263

2007

Okita, T., Sato, T., Sekimura, N.,
Iwai, T., Garner, F.A.

The Synergistic Influence of Temperature andDisplacement Rate on Microstructural Evolution of
Ion-Irradiated Model Austenitic Alloy Fe-15Cr-16Ni

Journal of Nuclear Materials

367-370, Part 2 (2007)
930-934

264

2007

Hu, Q., Sharafat, S., Ghoniem, N.

Modeling Space-Time Dependent Helium Bubble
Evolution in Tungsten Armor Under IFE Conditions

Fusion Science & Technology

52 [3] (2007) 574-578

Ideal Interfacial Strength Between Vanadium andOxide Ceramics

A−80

Second International Conference
on Multiscale Materials Modeling
Proceedings (2004)

329-333 (2004)
1571-1574

135-137

85 No.18/21 (2005) 2033

CHAPTER5TITAN
1.JournalPaper
Task11䚷Tritiumandmasstransferinfirstwall
Year

1

2007

D. Nishijima, R. P. Doerner, M. Spectroscopic determination of the singly ionized helium
J. Baldwin, E. M. Hollmann,density in low electron temperature plasmas mixed withand R. P. Seraydarian, Y. Ueda helium in a linear divertor plasma simulator

Phys. Plasmas

2

2007

S. Kajita, S. Takamura, N.
Ohno, T. Nishimoto

Alleviation of Damaged Tungsten Having Helium
Holes/Bubbles by Use of Transient Heat Load

Plasma Fusion Res.

3

2007

N. Ohno, S. Kajita, D.
Nishijima, S. Takamura

Surface Modification at Tungsten and Tungsten coatedGraphite due to Low Energy and High Fluence Plasma andLaser Pulse Irradiation

J. Nucl. Mater.

363-365 (2007) 1153-1159

4

2007

S. Kajita,S. Takamura, N.
Ohno,D. Nishijima,H. Iwakiri,
N. Yoshida

Sub-ms Laser Pulse Irradiation on Tungsten Target Damaged
by Exposure to Helium Plasma

Nucl. Fusion

47 (2007) 1358-1366

5

2007

S.Kajita, N.Ohno, S.Takamura, Plasma-assisted Laser Ablaion of Tungsten: Reduction in
W.Sakaguchi, D.Nishijima
Ablation Power Threshold Due to Bursting of Holes/Bubbles

Applied Phys. Let.

91 (2007) 261501

6

2008

M.J. Baldwin and R.P. Doerner Helium induced nanoscopic morphology

Nucl. Fusion

48 (2008) 035001

7

2009

S.Kajita, N.Ohno,
W.Sakaguchi, M.Takagi

Visualized blow-off from helium irradiated tungsten in
response to ELM-like heat load

Plasma Fusion Res.

8

2009

S.Kajita, S.Takamura, N.Ohno

Prompt ignition of a unipolar arc on helium irradiatedtungsten

Nucl. Fusion

49 (2009) 032002

9

2009

W.Sakaguchi, S.Kajita,
N.Ohno, M.Takagi

In situ reflectivity of tungsten mirrors under helium plasma
exposure

J. Nucl. Mater.

390-391 (2009) 179-182

10

2009

S.Kajita, W.Sakaguchi, N.Ohno

Formation and mitigation of fiberform nanostructured
tungsten by helium and sub-ms laser pulse irradiations

Plasma Devices andOperations

17 (2009) 165-173

11

2009

Shin Kajita, Shuichi Takamura Prompt ignition of a unipolar arc on helium irradiatedand Noriyasu Ohno
tungsten

Nucl. Fusion

49 (2009) 032002

12

2009

Shin Kajita, Wataru Sakaguchi,
Formation process of tungsten nanostructure by the exposure
Nucl. Fusion
Noriyasu Ohno, Naoaki
to helium plasma under fusion relevant plasma conditions
Yoshida, Tsubasa Saeki

49 (2009) 095005

13

2009

N.Ohno, M.Yoshimi,
M.Tokitani, S.Takamura,
K.Tokunaga, N.Yoshida

14

2009

Effect of bulk temperature on erosion of tungsten plasmaK R Umstadter, R Doerner andfacing components subject to simultaneous deuterium plasma Phys. Scr.
G Tynanand heat pulses

15

2009

K.R. Umstadter, R. Doerner, G. Enhanced erosion of tungsten plasma-facing components
Tynan
subject to simultaneous heat pulses and deuterium plasma

J. Nucl. Mater.

386–388 (2009) 751–755

16

2009

M. Miyamoto, D. Nishijima, Y. Observations of suppressed retention and blistering for
Ueda, R.P. Doerner
tungsten exposed to deuterium–helium mixture plasmas

Nucl. Fusion

49 (2009) 065035

17

2009

M.J. Baldwin, R.P. Doerner, D.
The effects of high fluence mixed-species (deuterium, helium,
Nishijima, K. Tokunaga, Y.
J. Nucl. Mater.
beryllium)
Ueda

390–391 (2009) 886–890

2010

K.Tokunaga, M.J. Baldwin, R.P.
Doerner, D. Nishijima, H.
Nanoscale surface morphology of tungsten induced by BeKurishita, T. Fujiwara, K. Araki,
J. Nucl. Mater.
seeded D-He plasma exposure
Y. Miyamoto, N. Ohno and Y.
Ueda

to be published18

Authors

Title of Paper

Spherical cauliflower-like caron dust formed by interaction
between deuterium plasma and graphite target and its
internal structure

A−81

JournalVol. (Year) Page (Start) -Page(End)or Identification No.

No

J. Nucl. Mater.

14 (2007) 103509

2 (2007) 9-10

4 (2009) 4

390-391 (2009) 61-64

T138 (2009) 014047

Task12䚷Tritiumbehaviorinblanketsystems
19

2008

S. Fukada, Y. Edao, Y. Maeda,
T. Norimatsu

20

2008

J. P. Sharpe, N.B. Morley, T.
Terai, T. Kunugi, T. Yokomine, US/Japan TITAN collaboration activities on tritium and MHD
K. Messadek, S. Smolentsev, S. flow control for lead-lithium eutectic blankets
Konishi, S. Fukada

TOFE-18

Sep-0821

2008

P. Calderoni, P. Sharpe, S.
Measurement of hydrogen and deuterium solubility in the
Konishi, K. Noborio, T. Kamei,
eutectic lead-lithium alloy Name of Conference
T. Terai

SOFT-25

Sep-0822

2008

Y. Maeda, S. Fukada, Y. Edao

Solubility, diffusivity and isotopic exchange rate of hydrogenisotopes in Li-Pb

Fusion Sci. Tech.

54 (2008) 131-134

23

2009

Y. Edao, S. Fukada, H.
Noguchi, Y. Maeda, K.
Katayama

Isotope effects of hydrogen isotope absorption and diffusion
in Li0.17Pb0.83 eutectic alloy

Fusion Sci. Tech.

56 (2009) 831-835

24

2009

D. Masuyama, T. Oda, S.
Fukada, S. Tanaka

Chemical state and diffusion behavior of hydrogen isotopes in
Chem. Phys. Let.
liquid lithium-lead

483 (2009) 214-218

25

2009

S. Fukada, Y. Edao, T.
Norimatsu

Design of tritium recovery system for laser fusion reactor

Annual Report of NIFS

(2009) 496

26

2010

Y. Edao, H. Noguchi, S. Fukada

Experiment of hydrogen isotopes permeating through Li-Pb
with diffusion, dissolution and isotopic exchange

J. Nucl. Mater.

submitted

27

2010

S. Fukada, Y. Edao

Unresolved issues on tritium mass transfer in Li-Pb liquidblankets

J. Nucl. Mater.

submitted

28

2010

S. Fukada, Y. Edao, A. Sagara

Effects of simultaneous transfer of heat and tritium throughLi-Pb or Flibe blanket

Fusion Eng. Des.

In press

29

2010

Y. Edao, H. Noguchi, S. Fukada

Isotopic exchange rate between hydrogen and deuterium inthe process of permeating through Li 0.17Pb0.83

Fusion Eng. Des.

In press

30

2010

R. Nadaoka, K. Uriu, Y.
Yamamoto, and S. Konishi

Difffusion and Solution of Hydrogen Isotopes in Lithium-Lead
BlanketProc. Of the 23rd SOFE

31

2010

S. Konishi and Y.Wu

LiPb blankets for TBM and DEMO

Fusion Eng. Des.

submitted

Tritium recovery system for Li-Pb of Inertial Fusion Reactor

Fusion Eng. Des.

83 (2008) 747-751

SP4A-4 (2010)

Task13䚷Flowcontrolandthermofluidmodeling
32

2007

J. Takeuchi, S. Satake, T.
Kunugi, T. Yokomine, N.
Morley, M. Abdou

Development Of PIV Technique Under Magnetic Fields And
Measurement Of Turbulent Pipe Flow Of Flibe Simulant Fluid

Fusion Sci. Tech.

52 (2007) 860-864

33

2007

T. Yokomine, J. Takeuchi, H.
Nakaharai, S. Satake, T.
Kunugi, N. Morley, M. Abdou

Experimental Investigation Of Turbulent Heat Transfer Of High
Fusion Sci. Tech.
Prandtl Number Fluid Flow Under Strong Magnetic Field

52 (2007) 625-629

34

2007

H. Nakaharai, J. Takeuchi, T.
Yokomine, T. Kunugi, S.
Satake, N. Morley, M. Abdou

The influence of a magnetic field on turbulent heat transfer of Experimental Thermal andhigh Prandtl number fluid
Fluid Science

32 (2007) 23–28

35

2007

S. Smolentsev, R. Moreau

One-Equation Model for Quasi-Two-Dimensional Turbulent
Magnetohydrodynamic Flows

Phys. Fluids

19 (2007) 078101

36

2007

A. Beltrán, S. Cuevas, S.
Smolentsev

Instabilities in the Flow past Localized Magnetic Fields

J. Phys.: Conference Series

64 (2007) 012009

37

2008

J. Takeuchi, S. Satake,
N.Morley, T. Kunugi, T.
Yokomine, M.Abdou

Experimental study of MHD effects on turbulent flow of Flibe
simulant fluid in a circular pipe

Fusion Eng. Des.

83 (2008) 1082–1086

38

2008

Y. Yamamoto, T. Kunugi, S.
Satake, S. Smolentsev

DNS and k–ε model simulation of MHD turbulent channel
flows with heat transfer

Fusion Eng. Des.

83 (2008) 1309-1312

39

2008

K. Yuki, M. Okumura, H.
Hashizume, S. Toda, N.
Morley, A. Sagara

Flow visualization and heat transfer characteristics for sphere- J. Thermophys. Heatpacked pipes
Transfer

A−82

22(4) (2008) 638-648

40

2008

S. Satake, N. Yoshida, T.
Kunugi, K. Takase, Y. Ose, T.
Kano

DNS of turbulent heat transfer under a uniform magnetic field
Fusion Eng. Des.
at high Reynolds number

83 (2008) 1092-1096

41

2008

S. Smolentsev, N.B. Morley, C. MHD and heat transfer considerations for the US DCLL blanket
Fusion Eng. Des.
Wong and M. Abdou
for DEMO and ITER TBM

83 (2008) 1788-1791

42

2008

S. Smolentsev, R. Moreau, M. Characterization of Key Magnetohydrodynamic Phenomena in
Fusion Eng. Des.
Abdou
PbLi Flows for the US DCLL Blanket

83 (2008) 771-783

43

2008

N. Morley, Y. Katoh, S.
Malang, B.A. Pint, A.R. Raffray, Recent Research and Development for the Dual-Coolant
S. Sharafat, S. Smolentsev,
Blanket Concept in the US
G.E. Youngblood

Fusion Eng. Des.

83 (2008) 920-927

44

2008

N. Morley, M.-J. Ni, R.
MHD simulations of liquid metal flow through a toroidallyMunipalli, P. Huang, M. Abdou oriented manifold

Fusion Eng. Des.

83 (2008) 1335-1339

45

2009

Y.Ueki, M.Hirabayashi,
T.Kunugi, T. Yokomine and K.
Ara

Acoustic Properties of Pb-17Li Alloy for Ultrasonic Doppler
Velocimetry

Fusion Sci. Tech.

56 (2009) 846-850

46

2009

N.Morley, A.Medina,
M.Abdou

Meaurement of Specific Electrical Contact Resistance Between
Fusion Sci. Tech.
SiC and Lead-Lithium Eutectic Alloy

56 (2009) 195-200

47

2009

S.Smolentsev, S. Malang

Double-Layer Flow Channel Insert for Electric and Thermal
Insulation in the Dual-Coolant Lead-Lithium Blanket

Fusion Sci. Tech.

56 (2009) 201-205

48

2009

N.Vetcha, S. Smolentsev,
M.Abdou

Theoretical Study of Mixed Convection in Poloidal Flows of
DCLL Blanket

Fusion Sci. Tech.

56 (2009) 851-855

49

2009

K. Messadek, M.Abdou

Experimental study of the MHD flow in a prototypic inlet
manifold section of the DCLL blanket

Magnetohydrodynamics

45 (2009) 233-238

50

2009

R. Moreau, S. Smolentsev, S.
CuevasFlow in an Insulating Rectangular Duct at the Entry of aMagnetMagnetohydrodynamics

45 (2009) 181-192

51

2010

S. Smolentsev, S. Cuevas, A.
Beltrán

Induced Electric Current-Based Formulation in Computationsof Low Magnetic Reynolds Number Magnetohydrodynamic
Flows

J. Comput. Phys

52

2010

S. Smolentsev, Z.Xu, Ch.Pan,
M.Abdou

Numerical and Experimental Studies of MHD flow in a
Rectangular Duct with a Non-Conducting Flow Insert

Magnetohydrodynamics

46 (2010) 99-111

53

2010

Y.Ueki, T.Kunugi, M. Kondo,
Consideration of Alumina Coating Fabricated by Sol-gel
A.Sagara, N.Morley, M.Abdou Method for PbLi Flow

Zero-Carbon Energy Kyoto
2009䚷(Springer Book)(2010) 373-379

54

2010

Y.Ueki, T.Kunugi, N.Morley,
M.Abdou

Fusion Eng. Des.

2010 in press

55

2010

S. Smolentsev, R. Moreau, L. B MHD Thermofluid Issues of Liquid-Metal Blankets:ühler, C. Mistrangelo
Phenomena and Advances

Fusion Eng. Des.

2010 in press

56

2010

S. Smolentsev, C. Wong, S.
MHD Considerations for the DCLL Inboard Blanket and Access
Fusion Eng. Des.
Malang, M. Dagher, M. Abdou Ducts

In press

2010

C.P.C. Wong, M. Abdou, M.
Dagher, Y. Katoh, R.J. Kurtz, S.
Malang, E.P. Marriott, B.J.
Merrill, K. Messadek, N.B.
An Overview of the US DCLL ITER-TBM Program
Morley, M.E. Sawan, S.
Sharafat, S. Smolentsev, D.K.
Sze, S. Willms, A. Ying, M.Z.
Youssef

In press

57

Consideration of Alumina Coating Fabricated by Sol-gel
Process as MHD Coating against Liquid Pb-17Li

A−83

Fusion Eng. Des.

229 (2010) 1558-1572

Task21䚷Irradiationtritiumsynergism

58

2008

Y. Oya, P. Calderoni, M.
Deuterium Retention and Desorption Behaviors in Tungsten
Shimada, Y. Hatano, R.
Exposed to TPE
Kolasinski, P. Sharpe, K. Okuno

SOFT-25

Sep. 15-19, 2008, Rostock,Germany

59

2009

Y. Hatano, M. Hara, Y. Oya, P.
Calderoni, P. Sharpe, M.
Tungsten Related Activities in Japan-US Joint Research Project
ICFRM-14
Shimada, Y. Katoh, T.
TITAN Task 2-1
Yamamoto

Sep. 6-11, 2009, Sapporo,
Japan

2009

Y. Oya, Y. Inagaki, S. Suzuki, H.
Ishikawa, Y. Kikuchi, A.
Behavior of hydrogen isotope retention in carbon implanted
Yoshikawa, T. Iwakiri, N.
tungsten
Ashikawa, A. Sagara, N.
Yoshida, K. Okuno

390-391 (2009) 622-625

61

2009

Y. Oya, S. Suzuki, W. Wang, R.
Kurata, M. Kobayashi, N.
Correlation between deuterium retention and microstructure
Phys. Scr.
Ashikawa, A. Sagara, N.
change for tungsten under triple ion implantation
Yoshida, K. Okuno

T138 (2009) 014051

62

2009

M. Kobayashi, S. Suzuki, W.
Wang, R. Kurata, K. Kida, N.
Ashikawa, A. Sagara, N.
Yoshida, Y. Oya, K. Okuno

Trapping behaviour of deuterium ions implanted into
tungsten simultaneously with carbon ions

T138 (2009) 014050

2010

R. D. Kolasinski, M. Shimada,T. Otsuka, J. M. Shea, T. R.
Allen, P. Calderoni, J. P.
Sharpe, and R. A. Causey

Hydrogen isotope retention, surface profile and depth profile
of polycrystalline tungsten exposed to high flux deuterium
Phys. Scr.
plasma60

63

J. Nucl. Mater.

Phys. Scr.

(2009) 014042

Task22䚷Joiningandcoatingintegrity

2007

N. Baluc, D. S. Gelles, S.
Jitsukawa, A. Kimura, R. L.
Status of Reduced Activation Ferritic/martensitic Steel
Klueh, G. R. Odette, B. van der Development
Schaaf and Jinnan Yu

J. Nucl. Mater

367-370 (2007) 33-41

65

2007

A. Kimura, R. Kasada, A.
Kohyama, H. Tanigawa, T.
Recent Progress in US-Japan Collaborative Research on
Hirose, K. Shiba, S. Jitsukawa,
Ferritic Steels R&D
S. Ohtsuka, S. Ukai, M.A.
Sokolov, et al.

J. Nucl. Mater

367-370 (2007) 60-67

66

2007

J.S. Lee, C.H. Jang, I.S. Kim and Embrittlement and Hardening during Thermal Aging of High Cr
J. Nucl. Mater
A. Kimura
Oxide Dispersion Strengthened Alloys

367-370 (2007) 229-233

67

2007

H.S. Cho, R. Kasada and A.
KimuraJ. Nucl. Mater

367-370 (2007) 239-243

68

2007

C.P.C. Wong, V. Chernov, A.
Kimura, Y. Katoh, N. Morley, T.
ITER-Test Blanket Module Functional Materials
Muroga, K.W. Song, Y.C. Wu
and M. Zmitko

J. Nucl. Mater

367-370 (2007) 1287-1292

69

2007

K. Yutani, H. Kishimoto, R.
Kasada and A. Kimura

Evaluation of Helium effects on Swelling Behavior of Oxide
Dispersion Strengthened Ferritic Steels under Ion Irradiation

J. Nucl. Mater

367-370 (2007) 423-427

70

2007

M.A. Sokolov, A. Kimura, H.
Tanigawa and S. Jitsukawa

Fracture Toughness Characterization of JLF-1 Steel after
Irradiation in HFIR to 5 dpa

J. Nucl. Mater

367-370 (2007) 644-647

71

2007

S.Ukai and S. Ohtsuka

Nano-mesoscopic Structural Control in 9Cr-ODS
Ferritic/martensitic Steels

Energy Mater.

2(1) (2007) 26-35

72

2007

E.M.Tabakin, S.V.Kuzmin,
Yu.V.Ivanovich, S.Ukai, et al.

Investigation of Y2O3 Distribution in Welding Joints of Thin
Claddings from Dispersion-hardened Steel

Atomic Energy102(6) (2007) 430

64

Effects of Neutron Irradiation on the Tensile Properties ofHigh-Cr Oxide Dispersion Strengthened Ferritic Steels

A−84

73

2007

S.Yamashita, N.Akasaka,
S.Ukai, et al.

Microstructural Development of a Heavily Neutron-irradiatedJ. Nucl. Mater.
ODS Ferritic Steel (MA957) at Elevated Temperature

74

2008

Y. Katoh, T. Hinoki, H.C. Jung,
J.S. Park, S. Konishi, M.
Ferraris

DEVELOPMENT AND EVALUATION OF SILICON CARBIDEJOINTS FOR APPLICATIONS IN RADIATION ENVIRONMENT

75

2009

C. Chun Fu, A. Kimura, M.
Samaras, M. Serrano de Caro, Materials for Future Fusion and Fission Technologies
R E. Stoller

76

2009

C. Park, K. Noborio, R. Kasada,Compatibility of materials for advanced blanket with liquid
Y. Yamamoto, G. Nam, S.
LiPb
Konishi77

2009

N. Okuda, R. Kasada, A.
KimuraStatistical evaluation of anisotropic fracture behavior of ODS
ferritic steels by using small push tests

J. Nucl. Mater.

386-388 (2009) 974-978

78

2009

Effects of helium on ductile-brittle transition behavior
䠝.Hasegawa, M. Ejiri, S.
ofreduced-activation ferritic steels after high-concentration
Nogami, M. Ishiga, R. Kasada,heliumimplantation at high temperatureJournal of Nuclear
A. Kimura, K. Abe,S. Jitsukawa
Materials

J. Nucl. Mater.

386-388 (2009) 241-244

79

2009

H.Kishimoto, R. Kasada, O.
Hashitomi, A. Kimura

Stability of Y–Ti complex oxides in Fe–16Cr–0.1Ti ODS ferritic
steel beforeand after heavy-ion irradiationJournal of Nuclear
Materials

J. Nucl. Mater.

386-388 (2009) 533-536H

80

2009

T. Nagasaka, R. Kasada, A.
Kimura, Y. Ueda, T. Muroga

Thermophysical properties and microstructure of plasmasprayed tungsten coating on low activation materials

Fusion Sci. Tech.

56 (2009) 1053-1057

81

2009

H. Watanabe, A. Higashijima,
The microstructure of laser welded Y doped V–4Cr–4Ti alloys
N. Yoshida, T. Nagasaka and T.
after ion irradiation
MurogaJ. Nucl. Mater.

386-388 (2009) 598-601

82

2009

N. Hara, S. Nogami, T.
Nagasaka, A. Hasegawa, H.
Tanigawa, T. Muroga

Mechanical Property Changes and Irradiation Hardening Due
to Dissimilar Metal Welding with Reduced Activation
Ferritic/Martensitic Steel and 316L Stainless Steel

Fusion Sci. Tech.

56 (2009) 318-322

2010

Naoko Oono, Sanghoon Noh,Noriyuki Iwata, Takuya
Nagasaka, Ryuta Kasada,
Akihiko Kimura

Metallurgical analysis of ODS steel/Tungsten joints

J. Nucl. Mater.

submitted

84

2010

R. Kasada, S.G. Lee, J. Isselin,
J.H. Lee, T. Omura, A. Kimura, Anisotropy in Tensile and Ductile-Brittle Transition Behavior ofJ. Nucl. Mater.
T. Okuda, M. Inoue, S. Ukai, S. ODS Ferritic Steels
Ohnuki, T. Fujisawa, F. Abe

submitted

85

2010

M. Nono, T. Nakajima, M.
Iwama, R. Kasada, A. Kimura

submitted

86

2010

Sanghoon Noh, R. Kasada䠈A.
Microstructure and Mechanical Properties of Friction Stir
Kimura, Seung Hwan C. Park,
Processed ODS ferritic steels
S. Hirano

J. Nucl. Mater.

submitted

87

2010

K. Yabuuchi, H. Yano, R.
Kasada, A. Kimura

Dose dependence of irradiaiton hardening of binary ferritic
alloys irradiated with Fe3+ ionsJ. Nucl. Mater.

submitted

88

2010

J. ISSELIN, R. Kasada, A.
Kimura, T. Okuda, M. Inoue, S. Evaluation of Fracture Behavior of Recrystallized and AgedUkai, S. Ohnuki, T. Fujiwara, T. High-Cr ODS Ferritic Steels
F. AbeJ. Nucl. Mater.

submitted

89

2010

H. Noto, S. Ukai, S. Hayashi
and A. Kimura

J. Nucl. Mater.

to be published83

Fusion Materials SemiAnnual Progress Reports

A−85

DOE/ER-0313/44 (2008)
26-32

Materials Research Society December 2-4, 2008, Boston,
Symposium Proceedings
Massachusetts, USA

23rd Symposium on Fusion
Engineering

SCC Behavior of SUS316L in The High Temperature Pressurized
J. Nucl. Mater.
Water Environment

Transient Liquid-Phase (TLP) Bonding of ODS Martensitic
Steels367-370 (2007) 202

May31-June 5, 2009,
San Diego,California, USA

90

2010

Y. Sugino, S. Ukai and S.
Hayashi

Directional Recrystallization of ODS Alloys by Means of Zone
Annealing

J. Nucl. Mater.

to be published

91

2010

M. Yamamoto, S. Ukai, S.
Hayashi, T. Kaito and S.
Ohtsuka

Reverse Phase Transformation from Ferrite to Austenite in
9CrODS Ferritic Steels

J. Nucl. Mater.

to be published

92

2010

S.Ukai, M. Yamamoto, N.
Chikata, S. Hayashi, T. Kaito, S.
Ultra High-Strength of AUSFOMed 9CrODS Ferritic Steels
Ohtsuka, T. Azuma and S.
OhsakiJ. Nucl. Mater.

to be published

93

2010

M. Ferraris, M. Salvo, V.
Casalegno, Y. Katoh, A.
Kohyama, T. Hinoki

Joining of SiC-based materials for nuclear energy applications

J. Nucl. Mater.

submitted

94

2010

Charles H. Henager, Jr.

Low-Activation Joining of SiC/SiC Composites for Fusion
Applications

J. Nucl. Mater.

submitted

95

2010

Hun-Chea Jung, Tatsuya
Hinoki, Yutai Katoh, Akira
KohyamaDevelopment of the testing method of shear stress for NITESiC joining material

J. Nucl. Mater.

submitted

96

2010

M. Ferraris, A. Ventrella, M.
Salvo, H. Shaohua, V.
Joining of SiC and SiC/SiC for nuclear applications
Casalegno, S. Rizzo, Y. Katoh,
H. Jung, T. Hinoki, A. Kohyama

Ceramic Engineering &Science Proceedings

submitted

97

2010

N. Hashimoto, H. Tanigawa, H. Multiple-beam Irradiation Effects in Electron-Beam-Welded
Kinoshita, and S. Ohnuki
F82H Joint

J. Nucl. Mater.

submitted

98

2010

H Seto, N. Hashimoto, H.
Kinoshita, and S. Ohnuki

Effects of multi-beam irradiation on defect formation in Fe-Cr
J. Nucl. Mater.
alloyssubmitted

99

2010

T. Nagasaka, T. Muroga, H.
Watanabe, R. Kasada, N.
Iwata, A. Kimura

Mechanical property of V-4Cr-4Ti alloy after first wall coatingwith tungsten

J. Nucl. Mater.

submitted

100

2010

N. Hashimoto, H. Seto, N.
Yamaguchi, H. Kinoshita, and
S. Ohnuki

Multiple-beam Irradiation Effects in Ferritic steels and EBWelded F82H Joint

Materials Research Society
2010 Spring Meeting

Apr. 5-9, 2010,
San Francisco, USA

Task23䚷Dynamicdeformation
101

2008

Y. Katoh, K. Ozawa, L.L. Snead, MECHANICAL CHARACTERIZATION OF SILICON CARBIDE
Y.B.Choi, T. Hinoki, A.
COMPOSITES FOR HFIR-18J EXPERIMENT IN UNIRRADIATED
Hasegawa
CONDITION

Fusion Materials SemiAnnual Progress Reports

DOE/ER-0313/45 (2008)
21-34

102

2008

Y. Katoh, Y.B.Choi, T. Hinoki

TITAN TASK 2-3 SILICON CARBIDE BEND STRESS RELAXATIONCREEP EXPERIMENT

Fusion Materials SemiAnnual Progress Reports

DOE/ER-0313/45 (2008) 140145

103

2009

Shuhei Nogami, Akira
Hasegawa, Takahide
Compatibility between SiC and Li ceramics for solid breeding
Murayama, Nobuyuki Otake, blanket system
Manabu Satou, Katsunori Abe

104

2009

T. Nozawa, T. Hinoki, A.
Hasegawa, A. Kohyama, Y.
Katoh, L.L. Snead, C.H.
Henager, J.B.J. Hegeman

105

2009

K. Shimoda,J.S. Park, T. Hinoki, Microstructural optimization of high-temperature SiC/SiC
A. Kohyamacomposites by NITE process

106

2009

K. Shimoda,A. Kohyama, T.
Hinoki

107

2008

Influence of pyrolytic carbon interface thickness on
K. Shimoda,J.S. Park, T. Hinoki,
microstructure and mechanical properties of SiC/SiC
A. Kohyamacomposites by NITE process

J. Nucl. Mater.

Recent advances and issues in development of silicon carbide
J. Nucl. Mater.
composites for fusion applications

J. Nucl. Mater.

High mechanical performance SiC/SiC composites by NITECOMPOSITES SCIENCE AND
process with tailoring of appropriate fabrication temperature
TECHNOLOGY
to fiber volume fraction

A−86

COMPOSITES SCIENCE ANDTECHNOLOGY

386-388 (2009) 218-221

386 (2009) 622-627

386 (2009) 634-638

69[10] (2009) 1623-1628

68[1] (2008) 98-105

108

2010

K. Abe, S. Nogami, A.
Hasegawa, T. Hinoki, T.
Nozawa

109

2010

2010

110

Study on Stress Relaxation Behavior of Silicon Carbide by BSR
methodJ. Nucl. Mater.

submitted

Y. B. Choi, T. Hinoki, K. Ozawa, Tansthickness Tensile Properties of NITE SiC/SiC Composite
Y. Katoh
Irradiated at High Temperature

J. Nucl. Mater.

submitted

Yutai Katoh, Tatsuya Hinoki,
Properties of Advanced SiC Fiber Composites Irradiated at
Kazumi Ozawa, Yong-Bum
High Temperatures: Results from US/Japan HFIR-18J
Choi, Akira Hasegawa, Lance L.
Experiment
Snead

J. Nucl. Mater.

submitted

Fusion Eng. Des.

In press.

CommonTask䚷MFE/IFEsystemintegrationmodeling
111

2010

Akio Sagara, Yuri Igitkhanov,Farrokh Najmabadi

Review of stellarator/heliotron design issues towards MFE
DEMO

112

2010

S. Fukada, Y. Edao, A. Sagara

Effects of simultaneous transfer of heat and tritium through Li
J. Nucl. Mater.
–Pb or Flibe blanket

In press.

2.ConferencePaper
Task11䚷Tritiumandmasstransferinfirstwall
No

Year

Authors

Title of Paper

Conference Name

Month Date, Year, Place, Country

1

2010

K.Tokunaga, M.J. Baldwin, D.
Nishijima, R.P. Doerner, S.
Nagata, B.Tsuchiya,H.
Properties of re-deposited layer formed by Be seeded D-He
Kurishita, T. Fujiwara, K.Araki, mixture plasma tungsten interactions
Y. Miyamoto, N. Ohno and Y.
Ueda

2

2010

T. Otsuka, M. Shimada, R.
Kolasinski, et al.

Application of tritium imaging plate technique to examine
tritium behaviors on the surface and in the bulk of plasma
exposed materials

PSI-19May. 24-28, 2010,
San Diego, USA

3

2010

T. Otsuka, M. Shimada, T.
Tanabe, et al.

Behavior of tritium near surface region of metals exposed totritium plasma

Tritium-9

Oct. 24-29, 2010, Nara, Japan

4

2010

Noriyasu Ohno, Shin Kajita,
Yuki Hirahata, Masato
Yamagiwa, Makoto Takagi

Influence of Crystallographic Orientation on Helium Bubble
and Fuzz Structure Formation in Tungsten

PSI-19

May 24-28, 2010,
San Diego, U.S.A.

5

2010

Y. Kikuchi, D. Nishijima, M.
Nakatsuka, K. Ando, T.
Experimental Study of Plasma-Material Interaction Under
Higashi, N. Fukumoto, M.
ELM-like Heat Loads
Nagata, R.P. Doerner, Y. Ueda

PSI-19

May 24-28, 2010,
San Diego, U.S.A.

6

2010

M. Miyamoto, D. Nishijima,
Microscopic Damage of Tungsten Exposed to DuetriumM.J. Baldwin, R.P. Doerner, Y.
Helium Mixture Plasma in PISCES and Its Impacts on Retention PSI-19
Ueda, Y. Yasunaga, N. Yoshida,
Property
and K. Ono

May 24-28, 2010,
San Diego, U.S.A.

PSI-19

May 24-28,2010,
San Diego,USA

Task12䚷Tritiumbehaviorinblanketsystems
7

2010

Y. Edao, H. Noguchi, H. Okitsu, Permeation behavior of two-component hydrogen isotopes in
Tritium-9
S. Fukadalithium-lead eutectic alloy

Oct. 24-29, 2010, Nara, Japan

8

2010

S. Konishi , T. Shibata, K.
Noborio, and Y. Yamamoto

Tritium-9

Oct. 24-29, 2010, Nara, Japan

9

2010

S. Konishi , M.Ichinose, and Y. Fusion-Biomass Hybrid Concept and its Implication in Fusion
Yamamoto
Development

23rd IAEA Fusion Energy
Conference

10-16 October 2010
Daejon, Republic of Korea

SOFT-26

Sep. 28- Oct. 1, 2010, Porto,
Portugal

Strategy for environmentally and socially attractive fusion
tritium system

Task13䚷Flowcontrolandthermofluidmodeling
10

2010

Y.Ueki, K.Nagai, T.Kunugi et al.

Contact Angle Measurement of Molten Lead-Lithium on
Silicon Carbide Surfaces

A−87Task21䚷Irradiationtritiumsynergism

11

2010

M. Shimada, Y. Hatano, P.
Calderoni, T. Oda, Y. Oya, M.
Sokolov, K. Zhang, R.
Kolasinski, J. P. Sharpe

12

2010

13

2010

Deuterium Retention in Neutron-Irradiated Tungsten and
Molybdenum Exposed to High Flux Plasma in TPE

PSI-19

May 24-28, 2010,
San Diego, USA

T. Oda, M. Shimada, K. Zhang,
P. Calderoni, Y. Oya, M.
Behavior of Hydrogen Isotopes Loaded into NeutronSokolov, R. Kolasinski, J. P.
Irradiated Tungsten by TPE Plasma Exposure
Sharpe, Y. Hatano

Tritium-9

Oct. 24-29, 2010, Nara, Japan

Masashi Shimada, Y. Hatano,
P. Calderoni, T. Oda, Y. Oya,First Results from Deuterium Retention in Neutron-IrradiatedM. Sokolov, K. Zhang, R.
Tungsten
Kolasinski, and J. P. Sharpe

10th International
Workshop on Hydrogen
Isotopes in Fusion Reactor
Materials

May 31- June 2, 2010
Pleasanton, California, USA

Task22䚷Joiningandcoatingintegrity
14

2010

R. Kasada, H. Takahashi, H.
Kishimoto, K. Yutani, A.
KimuraSuperior Radiation Resistance of ODS Ferritic Steels

PRICM7

August 1-6, 2010, Cairns,
Australia

15

2010

K. Yabuuchi, M. Saito, R.
Kasada, A. Kimura

Neutron Irradiation Hardening of Fe-based Binary Alloys

PRICM7

August 1-6, 2010, Cairns,
Australia

16

2010

Y.Takayama, R.Kasada,
K.Yabuuchi, A.Kimura,
D.Hamaguchi, M.Ando,
H.Tanigawa

Evaluation of irradiation hardening of Fe-ion irradiated F82H
by nano-indentation techniques

PRICM7

August 1-6, 2010, Cairns,
Australia

17

2010

Sanghoon Noh, R. Kasada, N.
Joining of ODS steels and Tungsten for Fusion Applications
Oono, T. Nagasaka, A. Kimura

PRICM7

August 1-6, 2010, Cairns,
Australia

A−88

CHAPTER6DoubletIII
1.JournalPaper
Title of Paper

Vol. (Year) Page (Start) Page(End) or Identification No.

No

Year

Authors

1

2001

H. Takenaga, et al.

Comparison of particle confinement in the high confinementmode plasmas with the edge localized mode of the Japan
Phys. Plasmas
Atomic Energy Research Institute Tokamak-60 Upgrade and
DIII-D tokamak

8 (2001) 1607-1611

2

2001

L.L. Lao, et al.

Dependence of Edge Stability on Plasma Shape and Local
Pressure Gradients in the DIII-D and JT-60U Tokamaks

Nucl. Fusion

41 (2001) 295-300

3

2001

H. Takenaga, et al.

Study of particle pumping characteristics for different
pumping geometries in JT-60U and DIII-D divertors

Nucl. Fusion

41 (2001) 1777-1767

4

2001

Y. Kamada, et al.

Extended JT-60U plasma regimes for high integrated
performanceNucl. Fusion

41 (2001) 1311-1325

5

2002

C.C. Petty, et al.

Analysis of current drive using MSE polarimetry without
equilibrium reconstruction

Nucl. Fusion

42 (2002) 1124-1133

6

2003

G.D. Porter, et al.

Simulation on of the effect of plasma flows in DIII-D, JET, andJ. Nucl. Mater.
JT-60U

7

2003

A. Loarte, et al.

Characteristics of type I ELM energy and particle losses inexisting devices and their extrapolation to ITER

Plasma Phys. Controll. Fusion

45 (2003) 1549-1569

8

2003

P. Gohil, et al.

Increased understanding of the dynamics and transport in
ITB plasmas from multi-machine comparisons

Nucl. Fusion

43 (2003) 708-715

9

2003

T. Fujita, et al.

Overview of JT-60U results leading to high integrated
performance in reactor-relevant regimes

Nucl. Fusion

43 (2003) 1527-1539

10

2005

N. Oyama, et al.

Energy loss for grassy ELMs and effects of plasma rotationon the ELM characteristics in JT-60U

Nucl. Fusion

45 (2005) 871-881

11

2005

S. Ide, et al.

Overview of JT-60U progress towards steady-state advanced
Nucl. Fusion
tokamak45 (2005) S48-S62

12

2006

R.J. La Haye, et al.

Cross-macine bench-marking for ITER of neoclassical tearing
Nucl. Fusionmode stabilization by electron cyclotron current drive

46 (2006) 451-461

13

2006

T. Fujita, et al.

Steady state operation research in JT-60U with extended
pulse length

Nucl. Fusion

46 (2006) S3-S12

14

2006

N. Oyama, et al.

Pedestal conditions for small ELM regimes intokamaks

Plasma Phys. Control. Fusion

48 (2006) A171-A181

15

2007

R. Prater, et al.

Stabilization and prevention of the 2/1 neoclassical tearing
mode for improved performance in DIII-D

Nucl. Fusion

47 (2007) 371-377

16

2007

D.C. McDonald, et al.

Recent progress on the development and analysis of the
ITPA global H-mode confinement database

Nucl. Fusion

47 (2007) 147-174

17

2007

J.D. Callen, et al.

Experimental tests of paleoclassical transport

Nucl. Fusion

47 (2007) 1449-1457

18

2007

C.F. Maggi, et al.

Characteristics of the H-mode pedestal in improved
confinement scenarios in ASDEX Upgrade, DIII-D, JET and JT- Nucl. Fusion
60U

47 (2007) 535-551

19

2007

K. Kamiya, et al.

Edge localized modes; Recent experimental findings andrelated issues

Plasma Phys. Controll. Fusion

49 (2007) s43-s62

20

2007

N. Aiba, et al.

Numerical Method for the Stability Analysis of Ideal MHD
Modes with a Wide Range of Toroidal Mode Numbers inTokamaks

Plasma Fusion Res.

2 (2007) 010_1-010_8

21

2007

A. Kojima, et al.

Numerical Simulation of a High-Brightness Lithium Ion Gun
for a Zeeman Polarimetry on JT-60U

Plasma Fusion Res.

2 (2007) S1104_1-S1104_4

A−89

Journal313-316 (2003) 1085-1088

22

2007

A.M. Garofalo, et al.

Stability and control of resistive wall modes in high beta, low
Nucl. Fusion
rotation DIII-D plasmas

23

2007

H. Reimerdes, et al.

Reduced Critical Rotation for Resistive-Wall Mode
Stabilization in a Near-Axisymmetric Configuration

Phys. Rev. Lett.

98 (2007) 055001_1-055004

24

2007

M. Takechi, et al.

Identification of a Low Plasma-Rotation Threshold for
Stabilization of the Resistive-Wall Mode

Phys. Rev. Lett.

98 (2007) 055002_1-055004

25

2007

J.E. Rice, et al.

Inter-machine comparison of intrinsic toroidal rotation in
tokamaks

Nucl. Fusion

47 (2007) 1618-1624

26

2007

H. Takenaga, et al.

Overview of JT-60U results for the development of a steadyNucl. Fusion
state advanced tokamak scenario

47 (2007) S563-S578

27

2008

A. Kojima, et al.

Development of a high-brightness and low-divergencelithium neutral beam for a Zeeman polarimetry on JT-60U

Rev. Sci. Instrum.

79 (2008) 093502_1093502_5

28

2008

A. Kirk, et al.

Comparison of the spatial and temporal structure of type-I
ELMs

J. Phys.: Conf. Ser.

123 (2008) 012011_1012011_10

29

2009

R.J. La Haye, et al.

Prospects for stabilization of neoclassical tearing modes byelectron cyclotron current drive in ITER

Nucl. Fusion

49 (2009) 045005_1045005_8

30

2009

M. Murakami, et al.

Off-axis neutral beam current drive for advanced scenario
development in DIII-D

Nucl. Fusion

49 (2009) 065031_1065031_8

31

2009

J.M. Park, et al.

Validation of on- and off-axis neutral beam current drive
against experiment in DIII-D

Phys. Plasmas

16 (2009) 092508_1092508_8

32

2009

P.B. Snyder, et al.

Pedestal stability comparison and ITER pedestal prediction

Nucl. Fusion

49 (2009) 085035_1085035_8

33

2009

N. Oyama, et al.

Overview of JT-60U results towards the establishment ofadvanced tokamak operation

Nucl. Fusion

49 (2009) 104007_1104007_16

34

2010

K. Kamiya, et al.

Zeeman polarimetry measurement for edge current density
Rev. Sci. Instrum.
determination using Li-beam probe on JT-60U

47 (2007) 1121-1130

81 (2010) 033502_1033502_8

2.ConferencePaper
Conference Name

Month Date, Year, Place,
Country

Comparison of large and small ELM regimes in JT-60U and
DIII-D

American Physical Society, 44th
Annual Meeting of the Divisionof Plasma Physics

Nov. 11-15, 2002, Orlando,
FloridaN. Oyama, et al.

Energy loss for grassy ELMs and effects of plasma rotationon the ELM characteristics in JT-60U

20th IAEA Fusion Energy
Conference (FEC2004)

Nov.1-6, 2004, Vilamoura,
Portugal

2006

R.J. La Haye, et al.

Evaluating electron cyclotron current drive stabilization ofneoclassical tearing modes in ITER- Implications ofExperiments in ASDEX-U, DIII-D, JET, and JT-60U

21st IAEA Fusion Energy
Conference (FEC 2006)

Oct.16-21, 2006, Chengdu, China

4

2006

D.C. McDonald, et al.

Multi-machine dimensionless transport experiments

21st IAEA Fusion Energy
Conference (FEC 2006)

Oct.16-21, 2006, Chengdu, China

5

2006

R. Prater, et al.

Prevention of the 2/1 neoclassical tearing mode in DIII-D

21st IAEA Fusion Energy
Conference (FEC 2006)

Oct.16-21, 2006, Chengdu, China

6

2006

J.E. Rice, et al.

Inter-machine comparison of intrinsic toroidal rotation

21st IAEA Fusion Energy
Conference (FEC 2006)

Oct.16-21, 2006, Chengdu, China

7

2008

R.J. La Haye, et al.

Prospects for stabilization of neoclassical tearing modes byelectron cyclotron current drive in ITER

22nd IAEA Fusion Energy
Conference (FEC 2008)

Oct.13-18, 2008, Geneva,
Switzerland

8

2008

G. Viad, et al.

Particle simulation of energetic particle driven
Alfv\'en modes

22nd IAEA Fusion Energy
Conference (FEC 2008)

Oct.13-18, 2008, Geneva,
Switzerland

9

2008

M. Murakami, et al.

Off-axis neutral beam current drive for advanced scenario
development in DIII-D

22nd IAEA Fusion Energy
Conference (FEC 2008)

Oct.13-18, 2008, Geneva,
Switzerland

No

Year

Authors

1

2002

T. Oikawa, et al.

2

2004

3

Title of Paper

A−90

CHAPTER7HFIR
1.JournalPaper
Authors

Title of Paper

Vol. (Year) Page (Start) Page(End) or Identification No.

No

Year

1

2000

N. Hashimoto, et al.

Microstructure of austenitic stainless steels irradiated at
J. Nucl. Mater.
400°C in the ORR and the HFIR spectral tailoring experiment

2

2000

E. Wakai, et al.

Tensile properties and damage microstructures in
ORR/HFIR-irradiated austenitic stainless steels

J. Nucl. Mater.

283-287 (2000) 435-439

3

2000

E. Wakai, et al.

Effect of helium production on swelling of F82H irradiated in
J. Nucl. Mater.
HFIR

283-287 (2000) 799-805

4

2000

R. L. Klueh, et al.

Embrittlement of reduced-activation ferritic/martensitic
steels irradiated in HFIR at 300°C and 400°C

J. Nucl. Mater.

283-287 (2000) 478-482

5

2000

Y. Miwa, et al.

Swelling of F82H irradiated at 673 K up to 51 dpa in HFIR

J. Nucl. Mater.

283-287 (2000) 334-338

6

2000

Y. Miwa, et al.

Microstructures in Ti–Al intermetallic compounds irradiatedJ. Nucl. Mater.
at 673 K in HFIR

283-287 (2000) 273-277

7

2000

K. Shiba, et al.

Tensile behavior of F82H with and without spectral tailoring J. Nucl. Mater.

283-287 (2000) 358-361

8

2000

L.L. Snead, et al.

In situ thermal conductivity measurement of ceramics in afast neutron environment

J. Nucl. Mater.

283-287 (2000) 545-550

9

2000

K. Shiba, et al.

Low-temperature irradiation effects on tensile and Charpy
properties of low-activation ferritic steels

J. Nucl. Mater.

283-287 (2000) 474-477

10

2002

E. Wakai, et al.

Swelling of cold-worked austenitic stainless steels irradiatedJ. Nucl. Mater.
in HFIR under spectrally tailored conditions

307-311 (2002) 352-356

11

2002

E. Wakai, et al.

Microstructural study of irradiated isotopically tailored F82H
J. Nucl. Mater.
steel

307-311 (2002) 203-211

12

2002

D. S. Gelles, et al.

Recent results for the ferritics isotopic tailoring (FIST)
experimentJ. Nucl. Mater.

307-311 (2002) 212-216

13

2002

N. Hashimoto, et al.

Pros and cons of nickel- and boron-doping to study helium
J. Nucl. Mater.
effects in ferritic/martensitic steels

307-311 (2002) 222-228

14

2002

S. Jitsukawa, et al.

Development of an extensive database of mechanical andphysical properties for reduced-activation martensitic steel
F82H

J. Nucl. Mater.

307-311 (2002) 179-186

15

2002

R.L. Klueh, et al.

Ferritic/martensitic steels – overview of recent results

J. Nucl. Mater.

307-311 (2002) 455-465

16

2002

E. Wakai, et al.

Effect of triple ion beams in ferritic/martensitic steel on
swelling behavior

J. Nucl. Mater.

307-311 (2002) 278-282

A−91

Journal

280 (2000) 186-195

17

2002

Y. Miwa, et al.

Irradiation-assisted SCC susceptibility of HIPed 316LN-IG
stainless steel irradiated at 473 K to 1 dpa

J. Nucl. Mater.

307-311 (2002) 347-351

18

2002

M. Ando, et al.

Evaluation of hardening behaviour of ion irradiated reduced
J. Nucl. Mater.
activation ferritic/martensitic steels by an ultra-microindentation technique307-311 (2002) 260-265

19

2002

G. E. Lucas, et al.

Recent progress in small specimen test technology

J. Nucl. Mater.

307-311 (2002) 1600-1608

20

2002

T. Sawai, et al.

Swelling behavior of TIG-welded F82H IEA heat

J. Nucl. Mater.

307-311 (2002) 312-316

21

2002

G. R. Odette, et al.

Some recent innovations in small specimen testing

J. Nucl. Mater.

307-311 (2002) 1643-1648

22

2003

E. Wakai, et al.

Swelling behavior of F82H steel irradiated by triple/dual ion
J. Nucl. Mater.
beams

318 (2003) 267-273

23

2004

H. Tanigawa, et al.

Microstructure property analysis of HFIR-irradiated reducedJ. Nucl. Mater.
activation ferritic/martensitic steels

329-333 (2004) 283-288

24

2004

T. Taguchi, et al.

Post irradiation plastic properties of F82H derived from theJ. Nucl. Mater.
instrumented tensile tests

335 (2004) 457-461

25

2004

S. Jitsukawa, et al.

Recent results of the reduced activation ferritic/martensitic
J. Nucl. Mater.
steel development329-333 (2004) 39-46

26

2004

K. Shiba, et al.

Reduced activation martensitic steels as a structural
material for ITER test blanket

J. Nucl. Mater.

329-333 (2004) 243-247

27

2004

T. Nozawa, et al.

Neutron irradiation effects on high-crystallinity and nearstoichiometry SiC fibers and their composites

J. Nucl. Mater.

329-333 (2004) 544-548

28

2004

T. Tsukada, et al.

Effects of water and irradiation temperatures on IASCC
susceptibility of type 316 stainless steel

J. Nucl. Mater.

329-333 (2004) 657-662

29

2004

M. Ando, et al.

Synergistic effect of displacement damage and helium
atoms on radiation hardening in F82H at TIARA facility

J. Nucl. Mater.

329-333 (2004) 1137-1141

30

2005

N. Okubo, et al.

Heat treatment effects on microstructures and DBTT of
F82H steel doped with boron and nitrogen

Mater. Trans.

46 (2005) 193-195

31

2005

E. Wakai, et al.

Effects of helium production and heat treatment on neutron
Mater. Trans.
irradiation hardening of F82H steels irradiated withneutrons

46 (2005) 481-486

32

2005

N. Okubo, et al.

Tempering treatment effect on mechanical properties of
F82H steel doped with boron and nitrogen

Mater. Trans.

46 (2005) 1779-1782

33

2005

E. Wakai, et al.

Radiation hardening and -embrittlement due to He
production in F82H steel irradiated at 250 °C in JMTR

J. Nucl. Mater.

343 (2005) 285-296

34

2006

E. Wakai, et al.

Mechanical properties of small size specimens of F82H steel Fusion Eng. Des.

A−92

81 (2006) 1077-1084

35

2006

R.L. Klueh, et al.

Mechanical properties of neutron-irradiated nickelcontaining martensitic steels: II. Review and analysis ofhelium-effects studies

J. Nucl. Mater.

357 (2006) 169-182

36

2006

R.L. Klueh, et al.

Mechanical properties of neutron-irradiated nickelcontaining martensitic steels: I. Experimental study

J. Nucl. Mater.

357 (2006) 156-168

37

2006

T. Sawai, et al.

Microstructural evolution of SINQ irradiated austenitic
stainless steels

J. Nucl. Mater.

356 (2006) 118-121

38

2006

E. Wakai, et al.

Effect of gas atoms and displacement damage on
mechanical properties and microstructures of F82H

J. Nucl. Mater.

356 (2006) 95-104

39

2007

M.A. Sokolov, et al.

Fracture toughness and Charpy impact properties of several
J. Nucl. Mater.
RAFMS before and after irradiation in HFIR367-370 (2007) 68-73

40

2007

M.A. Sokolov, et al.

Fracture toughness characterization of JLF-1 steel after
irradiation in HFIR to 5 dpa

J. Nucl. Mater.

367-370 (2007) 644-647

41

2007

E. Wakai, et al.

Effect of heat treatments on tensile properties of F82H steel
J. Nucl. Mater.
irradiated by neutrons

367-370 (2007) 74-80

42

2007

M. Ando, et al.

Creep behavior of reduced activation ferritic/martensitic
steels irradiated at 573 and 773 K up to 5 dpa

J. Nucl. Mater.

367-370 (2007) 122-126

43

2007

N. Okubo, et al.

Effects of heat treatment and irradiation on mechanicalproperties in F82H steel doped with boron and nitrogen

J. Nucl. Mater.

367-370 (2007) 107-111

44

2007

H. Tanigawa, et al.

Radiation induced phase instability of precipitates in
reduced-activation ferritic/martensitic steels

J. Nucl. Mater.

367-370 (2007) 132-136

45

2007

T. Yamamoto, et al.

The transport and fate of helium in nanostructured ferritic
J. Nucl. Mater.
alloys at fusion relevant He/dpa ratios and dpa rates

367-370 (2007) 399-410

46

2007

G.E. Lucas, et al.

The role of small specimen test technology in fusion
J. Nucl. Mater.
materials development

367-370 (2007) 1549-1556

47

2007

R.L. Klueh, et al.

Mechanical properties of irradiated 9Cr–2WVTa steel withand without nickel

J. Nucl. Mater.

367-370 (2007) 102-106

48

2007

A. Kimura, et al.

Recent progress in US–Japan collaborative research on
ferritic steels R&D

J. Nucl. Mater.

367-370 (2007) 60-67

49

2007

R.J. Kurtz, et al.

The transport and fate of helium in martensitic steels at
fusion relevant He/dpa ratios and dpa rates

J. Nucl. Mater.

367-370 (2007) 417-422

50

2007

T. Nozawa, et al.

The effects of neutron irradiation on shear properties ofmonolayered PyC and multilayered PyC/SiC interfaces of
SiC/SiC composites

J. Nucl. Mater.

367-370 (2007) 685-691

51

2007

Y. Miwa, et al.

SCC behavior of solid-HIPed and irradiated type 316LN-IG
stainless steel in oxygenated or hydrogenated water at 423– J. Nucl. Mater.
603 K

367-370 (2007) 1175-1179

52

2007

H. Tanigawa, et al.

Irradiation effects on precipitation and its impact on themechanical properties of reduced-activation
ferritic/martensitic steels

A−93

J. Nucl. Mater.

367-370 (2007) 42-47

53

2008

H. Tanigawa, et al.

Technical issues of reduced activation ferritic/martensitic
steels for fabrication of ITER test blanket modules

Fusion Eng. Des.

83 (2008) 1471-1476

54

2008

R.L. Klueh, et al.

Mechanical properties of unirradiated and irradiatedreduced-activation martensitic steels with and without
nickel compared to properties of commercial steels

J. Nucl. Mater.

374 (2008) 220-228

55

2008

R.L. Klueh, et al.

Embrittlement of irradiated ferritic/martensitic steels in the
J. Nucl. Mater.
absence of irradiation hardening

377 (2008) 427-437

56

2008

R.L. Klueh

Reduced-activation steels: Future development for
improved creep strength

378 (2008) 159-166

57

2009

S. Jitsukawa, et al.

Irradiation effects on reduced activation ferritic/martensitic
Nucl. Fusion
steels – tensile, impact, fatigue properties and moldeling

58

2009

Y. Miwa, et al.

Stress corrosion cracking susceptibility of a reducedactivation martensitic steel F82H

J. Nucl. Mater.

386-388 (2009) 703-707

59

2009

T. Yamamoto, et al.

Helium effects on microstructural evolution in tempered
martensitic steels: In situ helium implanter studies in HFIR

J. Nucl. Mater.

386-388 (2009) 338-341

60

2009

M. Ando, et al.

Effect of two-steps heat treatments on irradiation hardening
J. Nucl. Mater.
in F82H irradiated at 573 K

386-388 (2009) 315-318

61

2009

T. Nozawa, et al.

The effect of neutron irradiation on the fiber/matrix
interphase of silicon carbide composites

J. Nucl. Mater.

384 (2009) 195-211

62

2009

R.L. Klueh, et al.

Embrittlement of irradiated F82H in the absence of
irradiation hardening

J. Nucl. Mater.

386-388 (2009) 191-194

63

2009

J. Nagakawa, et al.

Creep behavior of the F82H steel under irradiation with 17
MeV protons at 300 °C

J. Nucl. Mater.

386-388 (2009) 264-267

64

2009

R.J. Kurtz, et al.

Recent progress toward development of reduced activation
J. Nucl. Mater.
ferritic/martensitic steels for fusion structural applications

386-388 (2009) 411-417

65

2010

E. Wakai, et al.

Reduction method of DBTT shift due to irradiation for
reduced-activation ferritic/martensitic steels

A−94

J. Nucl. Mater.

J. Nucl. Mater.

49 (2009) 115006

398 (2010) 64-67

Appendix B
Statistics and Related Documents
B.1 Workshop & Personnel
B.2 Table of Safety Trips

B.1 Workshop & Personnel
Number of Workshops
100Japan to US
US to Japan

75

50

25

0
2000

2001

2002

2003

2004

2005

2006

2007

2008

2009

Year

Number of Personnel Exchanges
200Japan to US
US to Japan
150

100

50

0
2000

2001

2002

2003

2004

Year
A−95

2005

2006

2007

2008

2009

A−96

B.2 Table of Safety Tripsth

5 :FuY1995(Japan>US)
Visited Sites:
University of Texas at Austin (TEXAS)

July 21,1995

Pacific Northwest Laboratory at Richland (PNL)

July 24

University of Wisconsin at Madison (WISC)

July 26

Massachusetts Institute of Technology (MIT)July 28

Princeton Plasma Physics Laboratory (PPPL)

July 31

Japanese Participants :Hideo Okada,Japan Atomic Energy Research Institute (7/21-7/31)

Hiromi Hirabayashi,

National Institute for Fusion Science (7/24-7/31)

Masatsugu Shimizu,

Japan Atomic Energy Research Institute (7/21-7/31)

Teruo Tamano,

University of Tsukuba (7/21-7/31)

Hiroaki Kurishita,

Tohoku University (7/24)

6th:FuY1996(US>Japan)
Visited Sites:
National Institute for Fusion Science (NIFS), Toki

June 19,1996

National Institute for Fusion Science (NIFS), Nagoya

June 20

Nagoya University

June 20

Kyoto University

June 21

Kyushu University

June 24

University of Tokyo

June 25

University of Tsukuba

June 26

Japan Atomic Energy Research Institute (JAERI)

June 27

US Participants :Richard L. Savercool,

General Atomics

Joseph A. Smith,

Princeton Plasma Physics Laboratory

7th:FuY1997(Japan>US)
Visited Sites:
Oak Ridge National Laboratory (ORNL)

July 9, 1997

General Atomics (GA)

July 11

University of California at San Diego (UCSD)

July 12

University of California at Los Angels (UCLA)

July 14

Lawrence Livermore National Laboratory (LLNL)

July 16

University of California at Davis, Livermore (UCD)

July 18

Japanese Participants :Keisuke Hasegawa,Japan Atomic Energy Research Institute

Masatsugu Shimizu,

Japan Atomic Energy Research InstituteYoichi Sakuma,

National Institute for Fusion Science

A−97

th

8 :FuY1999(US>Japan)
Visited Sites:
Japan Atomic Energy Research Institute (JAERI)

November 1, 1999

University of Tsukuba

November 2

Tohoku University

November 4

University of Tokyo

November 5

National Institute for Fusion Science (NIFS)

November 8

Nagoya University

November 9

Kyushu University

November 10

Osaka University

November 11

Kyoto University

November 12

Toyama University

November 15

US Participants :Richard L. Savercool,

General Atomics

Lee. Cadwallader,

Idaho National Engineering & Environmental Laboratory

9th:FuY2001(Japan>US)
Visited Sites:
Massachusetts Institute of Technology (MIT)March 18, 2002

Princeton Plasma Physics Laboratory (PPPL)March 19

University of California at San Diego (UCSD)

March 20

General Atomics (GA)March 20

Lawrence Berkeley National Laboratory (LBNL)

March 21

Lawrence Livermore National Laboratory (LLNL)

March 21

Japanese Participants :Yuichi Takase,

University of Tokyo

Naoyuki Miya,

Japan Atomic Energy Research InstituteKozo Matsushita,Japan Atomic Energy Research InstituteTatsuhiko Uda,

National Institute for Fusion Science

Ken’ichi Takagi,

National Institute for Fusion Science

Isao Ohtake,National Institute for Fusion Science

10th:FuY2003(US>Japan)
Visited Sites:
Tohoku University

February 16, 2004

National Institute for Fusion Science (NIFS)

February 18

Nagoya University

February 19

University of Tokyo

February 20

Japan Atomic Energy Research Institute (JAERI)

February 23

University of Tsukuba

February 24

Kyoto University

February 25

Osaka University

February 26

Kyushu University

February 25

US Participants :Richard L. Savercool,

General Atomics (2/14-2/28)

Mathew Fulton,

Massachusetts Institute of Technology (2/14-2/19)

Michael Viola,

Princeton Plasma Physics Laboratory (2/14-2/19)

Lee. Cadwallader,

Idaho National Engineering & Environmental Laboratory(2/19-2/28)

A−98

th

11 :FuY2005(Japan>US)
Visited Sites:
Princeton Plasma Physics Laboratory (PPPL)

February 22, 2006

Laboratory for Laser Energetics of Univ. Rochester

February 23

Oak Ridge National Laboratory (ORNL)

February 24

General Atomics (GA)

February 27

University of California at San Diego (UCSD)

February 27

Japanese Participants :Hiromi Hayashi,

National Institute for Fusion Science

Nobuyuki Hosogane,Japan Atomic Energy Agency

Akira Kohyama,

Kyoto University

Takayoshi Norimatsu,

Osaka University

Yuichi Takase,

University of Tokyo

Tatsuhiko Uda,

National Institute for Fusion Scienceth

12 :FuY2007(US>Japan)
Visited Sites:
University of Tokyo

March 10, 2008

University of Tsukuba

March 11

Tohoku University

March 12

Kyoto University, Yoshida

March 13

Kyoto University, Uji

March 14

Kyushu University

March 17

Osaka University

March 18

National Institute for Fusion Science (NIFS)

March 19

Japan Atomic Energy Research Institute (JAERI)

March 21

US Participants :Richard L. Savercool,

General Atomics

Keith Rule,

Princeton Plasma Physics Laboratory

Lee. Cadwallader,

Idaho National Engineering & Environmental Laboratory

13th:FuY2009(Japan>US)
Visited Sites:
General Atomics (GA)

February 22, 2010

Massachusetts Institute of Technology (MIT)February 23

Princeton Plasma Physics Laboratory (PPPL)

February 24

University of Wisconsin at Madison (WISC)

February 25

Japanese Participants :Kiyohiko Nishimura,

National Institute for Fusion Science

Yuichi Takase,

University of Tokyo

Tetsuo Seki,

National Institute for Fusion Science

Atsuhiko M. Sukegawa,Japan Atomic Energy Agency

A−99