National Institute for Fusion Science (NIFS)
National Institutes of Natural Sciences (NINS)

External Peer Review Reports in FY2013

March, 2014

External Peer Review Committee, NIFS Advisory Committee

Contents
Chapter

1 Background ···················································· 1

Chapter

2 Reviews and Proposals ···································· 4
2.1 Summary of reviews ·················································· 4
2.2 Proposals ······························································· 9

Chapter

3 In Closing ······················································ 11

Documents

2013 External Peer Review Presentation Materials

Appendix: Charts of review results

Chapter 1

Background

The National Institute for Fusion Science (hereafter as NIFS) was established in 1989 as aninter-university research institute, with the Large Helical Device (hereafter as LHD) as its principal
experimental device, in order to promote fusion research in universities. The planned LHD, bearing
the fusion community’s consensus and expectations, and characterized by its superconducting
Heliotron-type magnetic confinement system, emerged from an idea unique to Japan and has been
independently conceived and developed in Japan. Together with generating high-performancehelical-type plasmas through its high-power heating system, the LHD is advancing experimental
research that aims to clarify physical and engineering issues that stare at the realization of a toroidal
magnetic field confinement fusion reactor. On the other hand, parallel to this, utilizing large-scale
simulations is essential in analyzing the complexities of fusion plasma. At NIFS, having introduced
the newest supercomputer and made it available for collaborative use to fusion theory researchers
throughout Japan, we are moving forward with leading-edge research.

Recently, there have been changes to the system for domestic academic research. Since 2004 NIFS
has been an institution within the National Institutes of Natural Sciences (hereafter as NINS), andhas advanced collaborative use and collaborative research. Since being incorporated, NINS has
introduced six-year mid-term goals and mid-term plans, and a system for undergoing annual
evaluations of progress. This annual evaluation focuses primarily upon management and operation,
and at NIFS receiving evaluations of research results by researchers outside NIFS was deemed to beimportant. Under the Advisory Committee, the External Peer Review Committee has been
established, and it conducts annual research evaluations. The items to be evaluated are decided uponat the Advisory Committee. Adding external members of the Advisory Committee and experts to the
Review Committee, the Committee members will conduct evaluations. The Review Committee
reports its results to the Advisory Committee, and NIFS, respecting the results of the evaluation,utilizes the results in improving research activities from the next year.

At NIFS, from 2010 began the second period for mid-term goals, and in order to strengthen further
the unifying core of NIFS as the Center of Excellence in the plasma and fusion research fields, we
composed research projects for the three fields of the LHD, theory simulation, and fusion
engineering, and initiated research planning for combining the research results from these fields inmoving toward realization of the fusion reactor. For this reason, in 2010 we undertook a
restructuring of the research organization within NIFS. In addition to placing all researchers in one
research department, we composed a structure that enables researchers to participate independently
in projects. Through these changes, coordination among the LHD, theory simulation, and fusion1

engineering projects became easier, and we have become able to respond to new topics in a timely
manner.

In the Advisory Committee, in order to confirm the results of the project system, first, in JFY2011,
we implemented an external peer review of the LHD Project and in 2012 of the Numerical
Simulation Research Project. Then, in this current year (2013) we decided to implement an external
peer review of the Fusion Engineering Research Project (hereafter as FERP), which is in the fusion
engineering field. We established an External Peer Review Committee that included the nine
members of the Advisory Committee who are not NIFS researchers and the four members fromforeign countries, and five other specialists.

In their first meeting held on October 11, 2013, the members discussed the review process anddetermined the overall objectives and individual items. On November 30, NIFS presented Fusion
Engineering Research Project activities in detail using viewgraphs and other materials, and answered
the questions from the reviewers. On January 28, 2014, reviewers gathered in subgroups and rated
the activities after resolving any outstanding issues. The reviewers then met on February 21 to
finalize their review and document this report.

This report consists of three chapters: “Background,” “Reviews and Proposals,” and “In Closing.”

The report will be submitted to the Advisory Committee of NIFS. After gaining the Advisory
Committee’s approval, the Director General of NIFS will submit the report to the President of its
parental body, NINS. The report will go through NINS to be submitted to the Administrative Council
and the Education and Research Council of NINS. After the approval of these councils, this reportwill be used as an appendix of NINS’s annual reports in “Annual Plan of NINS (JFY2014)” and“Report of Achievements of Business Work in JFY2013” to be submitted to the Ministry of
Education, Culture, Sports, Science and Technology. The report will be available to public on the
web and in print.

In the evaluation of the Fusion Engineering Research Project, in the mid-term planning stipulated by
NINS the basis of the evaluation is the degree of completion of the Fusion Engineering Research
Project on which NIFS is advancing, and which has the goals of establishing the fusion reactor
design and the engineering base for the reactor, as well as the research standards.
It should be noted that these items of evaluation are based on the proposals from the external
evaluation of fusion engineering research, conducted in JFY2009.
2

1. Whether or not fusion engineering research is developing across the board with the emphasis on
helical reactors design
2. Whether or not NIFS is acting as the center for national research on advanced blankets andreduced activation materials as well as taking the leadership in terms of international research
3. Whether or not NIFS continues to develop superconducting coils for fusion reactor development
4. Whether or not efforts are being made to encourage young researchers to participate in the fusion
reactor research project
5. Whether or not the fusion engineering research project conducted by NIFS contributes tothe establishment of academic fundamentals for helical fusion reactors
The following is a list of this year’s evaluation items on the Fusion Engineering Research Project:[1] Establishment of research system and environment(1) Whether or not the target of FERP, initiated in JFY2010, is appropriate(2) Whether or not the organization of FERP is coincident with its target and properly functioning(3) Whether or not an appropriate research environment is provided for the establishment of
academic fundamentals[2] Research achievements
Whether or not FERP is achieving internationally praised results through the study of the helicalfusion reactor(1) Helical fusion reactor design(2) R&D toward establishment of the engineering basis[3] Encouragement of joint activities and collaborative research(1) Whether or not NIFS is promoting collaboration as a COE, focusing the high-level researchabilities of universities and research institutes(2) Whether or not NIFS is contributing to the development of research at universities(3) Whether or not FERP is collaborating with and contributing to international activities of ITER,
BA, and others[4] Human resources development
Whether or not FERP is nurturing young researchers who will support the long-term growth ofinternational fusion research[5] Future plans
Whether or not the future plan is pointing appropriately toward the medium- to long-term targets
3Chapter 2

Reviews and Proposals

Here is a summary of the comments and arguments given by the reviewers. This is followed byproposals which will be important in advancing the FERP research.

2.1 Summary of reviews[1] Establishment of research system and research environment(1) Whether or not the target of FERP, initiated in JFY2010, is appropriate
Regarding the important issues of reactor engineering that also are consistent with those fortokamak reactors, as a research center in Japan, together with establishing an engineering basethrough a helical fusion reactor design and taking into account previous suggestions, NIFS ismoving forward with setting objectives while planning the consistency of the reactor design andthe engineering bases. We can say that appropriate objectives are being set as objectives for
the Fusion Engineering Research Project, and we rate this highly.
On the other hand, as research by NIFS and universities, integration as a complete fusion
reactor founded upon academic, elemental research is important. And we hope that while
paying attention to complementarity and supplementation with tokamak reactors there will be
flexible responses to both long-term objectives and short-term objectives and their feasibility.

(2) Whether or not the organization of FERP is coincident with its target and properly
functioning
By shifting to a project system NIFS has become able to promote flexible research activities
that can be pushed forward while aiming at organic collaboration with numerous related
researchers within NIFS. Further, able to proactively advance collaborative research with
universities and other institutions, by forming a domestic center, promoting cooperation acrossprojects, allotting topics within the group, and actively placing young leaders, NIFS isconstructing a system that considers the development of human resources. Accordingly, wehighly rate this construction of a system that accords with the project’s goals and isfunctioning appropriately.
On the other hand, construction of a system for revising each task and feedback from reactor
design to experiments and R&D groups are necessary. Further, we hope for the enhancement ofresearchers moving forward proactively with fusion engineering.
4

(3) Whether or not an appropriate research environment is provided for the establishment of
academic fundamentals
Through continuous effort including a large-scale supplementary budget, high-level
experimental equipment as well as research tools are available. That an environment in which
it is possible to construct an infrastructure for engineering is being appropriately
advanced is highly rated.
Hereafter, it will be important that there be a research structure that includes researchers
throughout Japan. Utilizing collaborative research, regarding the maintenance and preservationof equipment that span several fields, through maintaining and increasing technical staff welook forward to the optimization of the operation of equipment as assets of the entire fusion
community.

[2] Research achievements
Whether or not FERP is achieving internationally praised results through the study of thehelical fusion reactor(1) Helical fusion reactor design
In the design of the helical fusion reactor, which is being emphasized in this project, that taking
the conceptual design based upon parameters obtained from the LHD as the standard andlinking the design to the Numerical Simulation Research Project indicated a way to self-ignition
is of great interest. In particular, this is an advanced conceptual design that incorporated issues
confined to the helical device and its strong points, such as the divertor configuration withneutron shielding. This conceptual design is of an extremely high level at the global level. It
may be said that this, more so than a comparison with tokamak reactors, is of more significanceas reactor design research by extracting engineering issues related to helical fusion reactors.
Accordingly, advancing the design for the helical fusion reactor and providing high-level
results at the international level is extremely highly rated.
By clarifying the process of design changes amid the flow of designs to this point, together withmoving forward with establishing the current understandings and issues feedback to the LHD
experiments is important. We hope for indications of the direction of engineering researchthrough written descriptions of the detailed examinations of edge plasma modeling, the heat
flux to the divertor, and alpha particles, and, further, through evaluation of the calculations
obtained from design and measurements obtained from experiments.
5(2) R&D toward establishment of the engineering basis
In developing basic equipment in response to the five issues mentioned above, while advancing
collaborative research together with outside researchers, research highly rated internationally is
being conducted. Further, including the broad linkages with universities and other research
institutions, together with the LHD Project and the Numerical Simulation Research Project,
NIFS is actively introducing distinctive cutting edge themes. We highly rate that suchresearch aiming at constructing engineering bases is being conducted, and that
researchers are producing research results of high levels internationally.
From now it may be said that it is necessary to concentrate not only on pioneering and creative
research, but also on basic engineering research development and trials and tests. In particular,
we look forward to even further advances regarding issues relating to the radiation technologies
such as neutrons and tritium necessary for the future fusion reactor, while examining efficient
ways of moving forward and planning country-wide linkages within the areas that only NIFS
can implement.

[3] Encouragement of joint activities and collaborative research(1) Whether or not NIFS is promoting collaboration as a COE, focusing the high-levelresearch abilities of universities and research institutes
Regarding the diverse research topics relating to reactor engineering, making use of generalcollaborative research, LHD project collaborative research, and bilateral collaborative research,collaborative research with numerous universities is being organically conducted. Further,regarding international cooperation, such as the Japan-United States collaborative research, theJapan-People’s Republic of China collaborative research, and other forms of international
cooperation, international collaborations are being undertaken through linkages with
universities with NIFS as the core. Through these activities, we highly rate the gathering of
high-level research abilities present at universities and other institutions and advancing
collaborative research appropriately as a Center of Excellence.
In the future, too, aware of the appraisal of the LHD as an international site, including theexchange of researchers, we look forward to the activities as the Center of Excellence ofdomestic fusion engineering research. In particular, together with strongly advancing
collaborative research in fields such as blankets, with which neutrons and tritium are related,
we look forward to NIFS’ role as a Center of Excellence with regard to strengthening society’s
6acceptance of fusion and the strengthening of safety.

(2) Whether or not NIFS is contributing to the development of research at universities
For undertaking collaborative research as well as research cooperation with numerous
universities that are linked to fusion engineering, and for contributing to the expansion of thebase of fundamental research in engineering, and for the construction and opening of thedatabase of atomic and molecular processes and plasma-wall interaction, we highly rate NIFS
for greatly contributing to the development of research at universities that aim atadvancing academic research.
In the future, advancing collaborative research on fusion engineering by using the leading edge
expert knowledge of researchers at NIFS and utilizing large-scale experiment facilities which
are difficult to implement in terms of maintenance, operation, funding, and personnel at thescale of a university laboratory, together with advancing further the germinating and pioneeringresearch at universities, we look forward to the composition of a database that records research
results and to the construction of a system that can widely utilize that information.

(3) Whether or not FERP is collaborating with and contributing to international activities of
ITER, BA, and others
To assist the ITER project and the BA activities, testing of the superconductor coils and NBI
performance is being conducted, which shows NIFS’s contribution to the ITER project and theBA activities by capitalizing upon the special characteristics of NIFS, which is endowed withspecialist research groups and large-scale equipment. Further, reactor engineering researchers at
NIFS serve at ITER and actively provide technological assistance in the ITER construction andare contributing to and expanding assistance to the ITER project and the BA activities.
Moreover, NIFS has a central role in achieving the planning and implementation of the joint
Japan-United States TITAN project and in the execution of the current PHENIX project. And
including the contributions to the Atoms and Molecules Database (GENIE), NIFS is providing
continuous contributions. Thus, we highly rate contributions to the ITER project and theBA activities as well as the linkages and contributions to international activities.
In the future, in the operation and execution of experiments in the LHD device beginning withsuperconducting coils technology, we look forward to further contributions to the ITER project,including the operation system, the training of operators, the safety system, and others
cultivated at NIFS. Further, regarding the BA activities which aimed at a prototype reactor, we
anticipate that this Fusion Engineering Research Project, which possesses great technological7

strength and abundant knowledge, will contribute greatly to research, including technologicaldevelopment and engineering verification, on a significant scale. Moreover, we look forward to
the clarification of the relationship with NIFS’ helical fusion reactor design, and to the positive
contributions of the prototype reactor design joint core team.

[4] Human resource development
Whether or not FERP is nurturing young researchers who will support the long-term growthof international fusion research
As a result of the appointment of young researchers as task leaders, brilliant young researchers
who will support fusion research are being nurtured, and numerous exceptional papers arebeing produced. Further, together with the education guidance that is being provided not only
for graduate students at Sōkendai but also for graduate students at Japanese universities andpost-doctoral researchers, the introduction of super science high schools (SSH), theimplementation of summertime experience enrollment to Sokendai and a steady approach thatwill educate human resources for the future are moving forward. Through these activities, werate highly these contributions to the nurturing of human resources who can participate
internationally and support the long-term development of fusion research.
Regarding the nurturing of human resources, emphasizing the standpoint of general engineeringof fusion research, through nurturing broadly human resources that will contribute todeveloping advanced science and industrial fields through linkages with universities, we greatly
look forward to the expansion of the human foundations of fusion research. Further, we
strongly hope for the implementation of measures, such as scholarships and the employment of
post-doctoral researchers that will seek to increase the research population in fusion. In
particular, in the future, it will be necessary to compose a structure for nurturing humanresources that follows the roadmap for realizing the fusion reactor and nurturing humanresources that support the fusion reactor’s safety, which is imperative. Moreover, we hope that
NIFS will aim to compose a structure that will make active participation in ITER and otherinternational programs by young researchers (including university researchers) possible.
For the nurturing of human resources, long-term and strategic approaches and indicators forappropriately evaluating results are necessary, and it should be urged to continuously engage indiscussions.

[5] Future plans
Whether or not the future plan is pointing appropriately toward the medium- to long-termtargets
8

Appropriate goal-setting regarding each element of technology development currently being
planned is being undertaken, and it may be said that a system for that purpose and equipment
enhancement, too, is being maintained satisfactorily. With regard to the goals that have been
established, from now, too, the capacity to continue undertaking appropriate researchdevelopment and system maintenance can be readily expected. Accordingly, the future
research plans that aim at goals are appropriate, and we rate highly the future plans
which gaze at mid- and long-term prospects.
On the other hand, it is necessary to clarify the specific road map for aiming toward realizationof the helical fusion reactor. Moreover, regarding research and development for the blanket, thedivertor, and other important equipment that integrate essential technologies, it will benecessary to clarify further the numerical objectives, the research issues, and the perspective on
achievement. At the same time, it will be necessary to also engage in technical issues such asfuel supply, assembly, maintenance, and remote handling. In the above project, a plan based
upon an international perspective is indispensable.
Moreover, through active contributions to the prototype reactor design core team, it will benecessary to distinguish among similarities, differences and complementarities in tokamaks andthe helical system, and to together search for means for development. It will be necessary to go
beyond differences in confinement methods and to pursue engineering similarities anduniversalities, and to evolve from “technology development” to “engineering bases.” We
anticipate that accumulating fundamental experimental data obtained from large-scaleequipment at NIFS and developing the database further will contribute to establishingspecifications and standards for the fusion reactor.
Through such research activities, we look forward to the nurturing of human resources that will
become the axis of advances in the ITER project and development of research on the prototype
reactor.

2.2 Proposals
Here is a summary of recommendations given by the panel to the NIFS Fusion Engineering
Project for its future operation.

(1) We look forward to the NIFS Fusion Engineering Project strengthening further the linkages
between the LHD Project and the Numerical Simulation Research Project, and together withplanning refinements in the helical fusion reactor design advances in strengthening
collaborative research in the superconducting coils, the divertor, the blanket, and other topics,
9

fulfilling the role as the Center of Excellence for developing fundamental technologies in thefusion engineering field, and evolving leading technologies that have been developed toward an
academic system as engineering.

(2) Nurturing young researchers who will lead the world in the fusion engineering field, including
too the ITER project and the BA activities, is an urgent task. We hope that universities andresearch institutes will construct linkages for realizing new frameworks for the nurturing of
human resources and the enhancement of their quality.

(3) We look forward to planning for the introduction of large-size experiment instruments and test
equipment in the fusion engineering field, which is difficult at universities, to the preparation ofresearch environments based upon the placement and increase of human resources, and to theconstruction of their maintenance and management systems, as well as to strongly advancing
the efficient application through collaborative use and research by universities and research
institutes.

(4) We look forward to the utilization of the technological results and the engineering expertisethat have been cultivated at NIFS, active participation in the ITER project and the BA activities,
as well as the accumulation of results and knowledge, the standardization of the fusion reactor
through the database, and contributions to the formation of standards.

10Chapter 3

In Closing

At NIFS, from 2010 the second period for mid-term goals began, and in order to strengthen further
the unifying core of NIFS as the Center of Excellence in the plasma and fusion research fields, we
composed research projects for the three LHD, theory simulation, and fusion engineering fields, andinitiated research planning for combining the research results from these fields in moving towardrealization of the fusion reactor. For this reason, in 2010 a restructuring of the research organization
within NIFS was undertaken. All researchers were placed in one research department, and a structure
was composed that enables researchers to participate independently in projects. Through thesechanges, linkages among the LHD, theory simulation, and fusion engineering projects are advanced,
and timely responses to new topics are anticipated.

In the Advisory Committee, in order to confirm the results of the project system, first, in 2011, we
implemented an external peer review of the LHD project and in 2012 the external peer review of the
Numerical Simulation Research Project. Then, in this current year (2013) we decided to implement
an external peer review of the Fusion Engineering Research Project, which is in the fusion
engineering field. We established an External Peer Review Committee that includes the nine
members of the Advisory Committee who are not NIFS researchers and the four members fromforeign countries, and five other specialists.

At the first meeting of the External Peer Review Committee, which was held on October 11, 2013,
we discussed how to advance with this year’s external peer review. It was decided to evaluate thepoints below.

[1] Establishment of research system and environment(1) Whether or not the target of FERP, initiated in JFY2010, is appropriate(2) Whether or not the organization of FERP is coincident with its target and properly functioning(3) Whether or not an appropriate research environment is provided for the establishment of
academic fundamentals[2] Research achievements
Whether or not FERP is achieving internationally praised results through the study of the helicalfusion reactor(1) Helical fusion reactor design(2) R&D toward establishment of the engineering basis11[3] Encouragement of joint activities and collaborative research(1) Whether or not NIFS is promoting collaboration as a COE, focusing the high-level researchabilities of universities and research institutes(2) Whether or not NIFS is contributing to the development of research at universities(3) Whether or not FERP is collaborating with and contributing to international activities of ITER,
BA, and others[4] Human resources development
Whether or not FERP is nurturing young researchers who will support the long-term growth ofinternational fusion research[5] Future plans
Whether or not the future plan is pointing appropriately toward the medium- to long-term targets

At their second meeting held on November 30, 2013, the panel was provided by the institute withdetailed information on the FERP activities along with the items above. On January 28, 2014, thereviewers gathered in subdivided groups and moved forward with the evaluation process. After all
the subgroups completed their proposals, the panel finalized its work in a report at its third meeting
held on February 21.

As results of this external peer review evaluation of the Fusion Engineering Research Project,regarding all of the items above, it has been concluded that in general they can be highly rated. In
particular, regarding research results relating to the helical fusion reactor design, this advanced
conceptual design incorporated strong points and issues unique to the helical system, and can be
extremely highly rated. Further, the setting of goals for the Fusion Engineering Research Project andthe propulsion system can be said to be appropriate and functioning organically, and this too can behighly rated. Moreover, that high-level experimental instruments and research equipment have been
introduced and a research environment is being provided, and that as a Center of Excellence in thisfield NIFS is contributing to research development at universities too can be highly rated. On theother hand, regarding research aimed at constructing a base for engineering, linkages with the ITER
project and the BA activities, and the nurturing of human resources, the constant visibility of effort
can be highly rated, though we look forward to still further development. Regarding future plans,
there is sound planning, which was well and carefully undertaken based upon achievements to date,
and this too can be highly rated. However, we look forward to efforts aimed at advancing academic
research that deepens further from “technology development” to “engineering bases.”
Still further, adding to these evaluation results, there are demands for the establishment of a system12regarding the efficient application of the experimental instruments and research equipment alreadyprovided and for construction of a new framework for nurturing young researchers who will lead theworld in the fusion engineering field, and we look forward to the realization of these demands aslinks with the fusion community.
To conclude, we have summarized below final comments regarding future ways of moving the
Fusion Engineering Research Project forward.

(1) We look forward to the NIFS Fusion Engineering Project strengthening further the linkages
between the LHD Project and the Numerical Simulation Research Project, and together withplanning refinements in the helical fusion reactor design advances in strengthening
collaborative research in the superconducting coils, the divertor, the blanket, and other topics,
fulfilling the role as the Center of Excellence for developing fundamental technologies in thefusion engineering field, and evolving leading technologies that have been developed toward an
academic system as engineering.

(2) Nurturing young researchers who will lead the world in the fusion engineering field, including
too the ITER project and the BA activities, is an urgent task. We hope that universities andresearch institutes will construct linkages for realizing new frameworks for the nurturing of
human resources and the enhancement of their quality.

(3) We look forward to planning for the introduction of large-size experiment instruments and test
equipment in the fusion engineering field, which is difficult at universities, to the preparation ofresearch environments based upon the placement and increase of human resources, and to theconstruction of their maintenance and management systems, as well as to strongly advancing
the efficient application through collaborative use and research by universities and research
institutes.

(4) We look forward to the utilization of the technological results and the engineering expertisethat have been cultivated at NIFS, active participation in the ITER project and the BA activities,
as well as the accumulation of results and knowledge, the standardization of the fusion reactor
through the database, and contributions to the formation of standards.

Based upon these suggestions, one may say that steadily advancing the Fusion Engineering Research
Project in the future will greatly contribute to the strengthening of the academic base and theresearch development systems in the fusion field.

13Documents

2013 External Peer Review Presentation Materials

2013 NIFS External Review (Nagoya, Dec. 2013)

Fusion Engineering
Research Project
in NIFS

Akio SAGARA
National Institute for Fusion Science
1 / 79

History of Fusion Engineering
Study in NIFS (1989 – 2004)

Fusion Engineering
Research Project
in NIFS

2013.4.25v1, 10.28v2, 10.29v3, 1 106v4
Year Engineering-related activities in NIFS
1987

1989 NIFS was establishedt bli h d

NIFS fusion engineering research andinternational cooperation（Japan and USA: FFTF/MOTA project wasstarted）
Research Operations Division（divertor）
Device Engineering Division（（superconductivity）
d i i ）
Safety and Environmental Research Center（tritium and safety）

Cryogenic Laboratory was completed
1990 Large superconducting magnet research anddevelopment
LHD helical coils winding machine1991 development
LHD inner vertical (IV) coils production
Production of superconducting conductor forhelical coil
1992
Construction of helium liquefaction
refrigerator for LHD
LHD inner shaping (IS) coil production
1993
LHD Building completion
NIFS collaboration on FFHR reactor design
was started
1994 Start of the joint research of helical type fusion
reactor design
Helical coil winding was started (1995/1)
LHD outer vertical (OV) coil production（Japan and USA: JUPITER project was
1995 Experiments on a Single Inner Vertical coilstarted）
was conducted
1996 Helical coils winding completion (1996/5)
LHD superconducting system was completed
1997 LHD first plasmaStart of the LHD experiment
1998
Fusion Engineering Research Center was
1999
established
Collaboration on Intense Neutron Source was
2000
started (up to 2004)

2004

1989 NIFS was established

Structural analysis and testing equipment (SUT) and Active
Cooling Test-stand (ACT) were introduced
Large superconducting test facility was introduced

Th

t

l

i

b NIFS

Cryogenic Laboratory was completed
1990 Large superconducting magnet research anddevelopment
LHD helical coils winding machinep1991 development
LHD inner vertical (IV) coils production
Production of superconducting conductor forhelical coil
1992
Construction of helium liquefaction
refrigerator for LHD
LHD inner shaping (IS) coil production
1993
LHD Building completion
NIFS collaboration on FFHR reactor design
was started
1994 Start of the joint research of helical type fusion
reactor design
Helical coil winding was started (1995/1)
LHD outer vertical (OV) coil production（Japan and USA: JUPITER project was
1995 Experiments on a Single Inner Vertical coilstarted）
was conducted
1996 Helical coils winding completion (1996/5)
LHD superconducting system was completed
1997 LHD first plasmaStart of the LHD experiment
1998
Fusion Engineering Research Center was
Fusion Engineering Research Center
1999
established(Materials, Blanket)
Collaboration on Intense Neutron Source was
2000
started (up to 2004)（Japan and USA: JUPITER-II project wasstarted）
2001(Japan and China: Core University Program(CUP) was started)

2004

Micro-hardness tester was introduced

The first mid-term goals and Start of themedium-term plan

F i Engineering
FusionE ii ResearchRh Laboratory
L b tbuilding opening

Fatigue testing equipment was introduced

The external peer review by NIFS
2009 Administrative Council on fusion engineeringresearch

Scanning electron microscope was introduced

2010

2011

2012

Structural analysis and testing equipment (SUT) and Active
Cooling Test-stand (ACT) were introduced
Large superconducting test facility was introduced

Micro-hardness tester was introduced

Fatigue testing equipment was introduced
Scanning electron microscope was introduced
30kg Vanadium ingot (NIFS-HEAT-1) production
170kg Vanadium ingot (NIFS-HEAT-2) production

X-ray photoelectron spectrometer was introduced

Device Engineering Division was renamed
Fusion and Advanced Technology System
Division and reorganized

Creep testing machine (Unit 1) was introduced

X-ray diffractometer was introduced（Japanp and USA: TITAN pprojectj
was started）
Creep testing machine (Unit 2) was introduced(BA-IFMIF/EVEDA Joint research wasstarted)（BA-Fusion reactor design R&D Joint research
Liquid lithium loop production and operation
was started）

Device Engineering and Advanced Physics
Research Division（Superconductivity、Tritiumand safety）

Fusion Engineering Research Project
Fusion Systems Research Division（Material,
was started
Interactive joint research (field of fusion
engineering) was started

30kg Vanadium ingot (NIFS-HEAT-1) production

The main fusion engineering researchequipments in NIFS

Osaka Univ.: Intense Neutron Source lithium target test
facility

National Institutes of Natural
Sciences was establishedThe external peer review by NIFS
Administrative Council on fusion engineeringresearch center
2005
The external peer review by Cryogenics andSuperconductivity Society of Japan onsuperconductivity and cryogenics group
Name changed from "Cryogenic laboratoriy"
2006
to "Superconducting magnet system laboratory2007

170kg Vanadium ingot (NIFS-HEAT-2) production

Device Engineering Division was renamed
Fusion and Advanced Technology System
Division and reorganized

NIFS fusion engineering research andinternational cooperation（Japan and USA: FFTF/MOTA project wasstarted）
Research Operations Division（divertor）
Device Engineering Division（superconductivity）
Safety and Environmental Research Center（tritium and safety）

2002（Post-CUP was started）

Production of particle dispersion strengthened vanadium
alloy（Japan and USA: PHENIX project wasstarted）

Variable temperature low temperature equipment(Supercritical helium generator etc. update）
Conductor magnet test facility（Including variable temperature current lead）
Heat and mass flow loop equipment (3T Orosh2i-2)
Transmission electron microscope（TEM)
Ultra-high vacuum creep testing machine
Joint fabrication and testing equipment (HIP, Ball mill etc.)
High power electron beam test-stand (300kW ACT-2)
Hydrogen accumulation analyzer（Tandem ion Accelerator, Surface Analyzer and SEM）
LHD irradiation testing equipment（FIB system, TDS etc.）
Hydrogen testing and measurement equipment（Gas composition analyzer, FTIR, etc.）

Helical reactor conceptual design interim
report

The external peer review by NIFS
2013 Administrative Council on Fusion

Engineering Research Project

Creep testing machine (Unit 3) was introduced

Blanket, Divertor）（Japan and China: Core University Program
was terminated）

Field emission scanning electron microscope was introduced
Molten salt loop (Orosh2i-1) production and operation

X-ray photoelectron spectrometer was introduced

Osaka Univ.: Intense Neutron Source lithium target test
facility

The first mid-term goals and Start of themedium-term plan

1987

The second mid-term goals and plan wasstarted

Fusion Engineering Research Center(Materials, Blanket)

2002

National Institutes of Natural
Sciences was established2013.4.25v1, 10.28v2, 10.29v3, 1 106v4
Year Engineering-related activities in NIFS

2008

（Japan and USA: JUPITER-II project wasstarted）(Japan and China: Core University Program(CUP) was started)

2001

The main fusion engineering researchequipments in NIFS

2 / 79Fusion Engineering
Research Project
in NIFS

History of Fusion Engineering
Study in NIFS (2004 – 2013)
facility

2004

National Institutes of Natural
Sciences was establishedThe first mid-term goals and Start of themedium-term plan2013.4.25v1, 10.28v2, 10.29v3, 1 106v4

Device Engineering Division was renamed
Fusion and Advanced Technology System
Division and reorganizedYear Engineering-related activities in NIFS
1987

1989 NIFS was establishedThe external peer review by NIFS
Administrative Council on fusion engineeringresearch centerTh externall peer review
Theib Cryogenics
by
C
i and
d
Superconductivity Society of Japan onsuperconductivity and cryogenics group
Name changed from "Cryogenic laboratoriy"
2006
to "Superconducting magnet system laboratory

Creepp testingg machine ((Unit 1)) was introduced

2005

2007

Fusion Engineering Research Laboratorybuilding opening

2008

X-ray diffractometer was introduced（Japan and USA: TITAN project was started）
Creep testing machine (Unit 2) was introduced(BA-IFMIF/EVEDA Joint research wasstarted)（BA-Fusion reactor design R&D Joint research
Liquid lithium loop production and operation
was started）

The external peer review by NIFS
2009 Administrative Council on fusion engineeringresearch

2012

Cryogenic Laboratory was completed
1990 Large superconducting magnet research anddevelopment
LHD helical coils winding machinep1991 development
LHD inner vertical (IV) coils production
Production of superconducting conductor forhelical coil
1992
Construction of helium liquefaction
refrigerator for LHD
LHD inner shaping (IS) coil production
1993
LHD Building completion
NIFS collaboration on FFHR reactor design
was started
1994 Start of the joint research of helical type fusion
reactor design
Helical coil winding was started (1995/1)
LHD outer vertical (OV) coil production（Japan and USA: JUPITER project was
1995 Experiments on a Single Inner Vertical coilstarted）
was conducted
1996 Helical coils winding completion (1996/5)
LHD superconducting system was completed
1997 LHD first plasmaStart of the LHD experiment
1998
Fusion Engineering Research Center was
1999
established
Collaboration on Intense Neutron Source was
2000
started (up to 2004)

FY2012 supplementary budget
Field emission scanning electron microscope was introduced

Helical reactor conceptual design interim
reportMolten salt loop (Orosh2i-1) production and operation

2005

2006

The external peer review by NIFS
2013 Administrative Council on Fusion

Engineering Research Project

Fusion Engineering
Research Project
in NIFS（Japan and USA: PHENIX project wasstarted）

Micro-hardness tester was introduced

30kg Vanadium ingot (NIFS-HEAT-1) production
170kg Vanadium ingot (NIFS-HEAT-2) production

X-ray photoelectron spectrometer was introduced

Osaka Univ.: Intense Neutron Source lithium target test
facility

National Institutes of Natural
Sciences was establishedThe first mid-term goals and Start of themedium-term plan

Device Engineering Division was renamed
Fusion and Advanced Technology System
Division and reorganized

The external peer review by NIFS
Administrative Council on fusion engineeringresearch center
The external peer review by Cryogenics andSuperconductivity Society of Japan onsuperconductivity and cryogenics group
Name changed from "Cryogenic laboratoriy"
to "Superconducting magnet system laboratory

FusionF
i Engineering
E i
i ResearchRh Laboratory
L b t
2007
building opening
2008

Creep testing machine (Unit 1) was introduced

X-ray diffractometer was introduced（Japanp and USA: TITAN pprojectj
was started）
Creep testing machine (Unit 2) was introduced(BA-IFMIF/EVEDA Joint research wasstarted)（BA-Fusion reactor design R&D Joint research
Liquid lithium loop production and operation
was started）

The external peer review by NIFS
2009 Administrative Council on fusion engineeringresearch
The second mid-term goals and plan wasstartedVariable temperature low temperature equipment(Supercritical helium generator etc. update）
Conductor magnet test facility（Including variable temperature current lead）
Heat and mass flow loop equipment (3T Orosh2i-2)
Transmission electron microscope（TEM)
Ultra-high vacuum creep testing machine
Joint fabrication and testing equipment (HIP, Ball mill etc.)
High power electron beam test-stand (300kW ACT-2)
Hydrogen accumulation analyzer（Tandem ion Accelerator, Surface Analyzer and SEM）
LHD irradiation testing equipment（FIB system, TDS etc.）
Hydrogen testing and measurement equipment（Gas composition analyzer, FTIR, etc.）

Structural analysis and testing equipment (SUT) and Active
Cooling Test-stand (ACT) were introduced
Large superconducting test facility was introduced

Scanning electron microscope was introduced

2002

2004

The main fusion engineering researchequipments in NIFS

Fatigue testing equipment was introduced

Fusion Engineering Research Center(Materials, Blanket)（Japan and USA: JUPITER-II project wasstarted）(Japan and China: Core University Program(CUP) was started)

2001

Device Engineering and Advanced Physics
The second mid-term goals and plan was
Research Division（Superconductivity、Tritium
startedand safety）
Fusion Engineering Research Project
2010
Fusion Systems Research Division（Material, Creep testing machine (Unit 3) was introduced
was started
Blanket, Divertor）
Interactive joint research (field of fusion（Japan and China: Core University Programengineering) was started
was terminated）
Production of particle dispersion strengthened vanadium
2011（Post-CUP（Post
CUP was started）
alloy

NIFS fusion engineering research andinternational cooperation（Japan and USA: FFTF/MOTA project wasstarted）
Research Operations Division（divertor）
Device Engineering Division（superconductivity）
Safety and Environmental Research Center（tritium and safety）

2010

Interactive joint research (field of fusion
engineering) was started
2011

2012

Device Engineering and Advanced Physics
Research Division（Superconductivity、Tritiumand safety）

Fusion Engineering Research Project
Fusion Systems Research Division（Material,
was started（Post-CUP was started）

Production of particle dispersion strengthened vanadium
alloy（Japan and USA: PHENIX project wasstarted）

Variable temperature low temperature equipment(Supercritical helium generator etc. update）
Conductor magnet test facility（Including variable temperature current lead）
Heat and mass flow loop equipment (3T Orosh2i-2)
Transmission electron microscope（TEM)
Ultra-high vacuum creep testing machine
Joint fabrication and testing equipment (HIP, Ball mill etc.)
High power electron beam test-stand (300kW ACT-2)
Hydrogen accumulation analyzer（Tandem ion Accelerator, Surface Analyzer and SEM）
LHD irradiation testing equipment（FIB system, TDS etc.）
Hydrogen testing and measurement equipment（Gas composition analyzer, FTIR, etc.）

Helical reactor conceptual design interim
report

The external peer review by NIFS
2013 Administrative Council on Fusion

Engineering Research Project

Creep testing machine (Unit 3) was introduced

Blanket, Divertor）（Japan and China: Core University Program
was terminated）

Field emission scanning electron microscope was introduced
Molten salt loop (Orosh2i-1) production and operation

3 / 79Points of Evaluation[1] Establishment of Research System and Environment
研究環境の整備[[2]] Research Achievements ~ Whether or not FERP is achievingg internationallyy
evaluated results throughout the study on helical fusion reactor
研究成果 〜ヘリカル型核融合炉の研究を進めることにより、国際的に⾼いレベルの成果を上げているか[3] Encouragement of Joint Activities and Collaborative
Research
共同利⽤・共同研究の推進[4] Human Resource Development ~ Whether or not FERP is bringing up young
researchers who can support long‐range growth of international fusion study
⼈材育成 〜核融合研究の⻑期的な発展を⽀える国際的に活躍できる⼈材の育成に貢献しているか[5] Future Plans ~ Whether or not the future plan is appropriately pointing at the medium‐to long‐term target
将来計画 〜⽬標に向けた今後の研究計画は適切か。特に、中⻑期的展望を⾒据えたものとなっているか
4 / 79Fusion Engineering
Research Project
in NIFS[1] Establishment of Research
System and Environment
研究環境の整備(1‐1) Whether or not the target of FERP, initiated in FY2010, isappropriate
平成２２年度にプロジェクトとして位置付けられた核融合⼯学研究プロジェクトの⽬標設定は適切か(1‐2) Whether or not the organization of FERP is coincident
with its target and properly functioning?
推進体制は⽬標に合致し、適切に機能しているか(1‐3) Whether or not an appropriate research environment isprovided for the establishment of academic fundamentals
⼯学基盤の構築を可能とする研究環境の整備は適切に進められているか

5 / 79Fusion Engineering
Research Project
in NIFS(1‐1) Target of FERP

FERP has been launched since 2010
With the target of

Promotion of conceptual and baseline designs towardrealization of a steady‐state helical fusion reactor andconstruction of engineering basis that enables real‐scaleand real‐environment R&D

定常ヘリカル型核融合炉実現に向けての概念及び基本設計の推進と、実規模・実環境試験を可能にする基幹⼯学
基盤の構築

Two keywords:y Conceptual design of helical reactor  Reactor Design
 Construction of engineering basis  R&D
Any researcher can participate in FERP, although the main body is theformer ‘Fusion Engineering Research Center (FERC)’
6 / 79Fusion Engineering
Research Project
in NIFSFERP as a ‘PROJECT’ of NIFS

Objectives andplans for the 2nd
mid‐term
Objectives to increase thequality of research andeducation in NINS“As one of the nation’s centers of excellence, NIFS intends to organize theacademic activities concerning fusion sciences and related fields atuniversities and other research institutes.
To achieve controlled thermonuclear fusion, meant to be environmentallysafe, NIFS will promote all fusion‐related research collaborations, includinginternationally coordinated activities towards nuclear fusion experiments,
based on the use of large experimental devices and computers.”

Action to achieve
the objectives“Research should be conducted for thedevelopment of blankets andsuperconducting coils along with efficient
reactor design
g activities, intendingg theestablishment of academic fundamentals.”

Promotion of
PROJECTs in NIFS

FERP
Fusion Engineering Research Project

・・・

・・・

LHD

NSRP

Large Helical
Device Project

Num. Sim.
Res. Project

7 / 79Fusion Engineering
Research Project
in NIFS

Roadmap of FERP

8 / 79Fusion Engineering
Research Project
in NIFS

Fusion Engineering

Mid‐ Term Schedule

eseach Project Mid- erm Plan

2010.9.24/ ev.10.7 A.

agara

I E

D

→ 2026FPBA
IFMIF-E IDA
J -60 A
LHD
I AN

2010
1〜3

6

2011
9 12

3

6

2012

9 12

3

6

2013

9 12

3

6

2014

9 12

3

6

2015

9 12

3

6

2016

9 12

3

6

2017

2018

2017

2018

9 12

econd Mid-term
I FN -10

OFE-20I FN -11

OFE-21I FN -12

OFE-22

As a group,

IAEA-23

ICF M-15

IAEA-24

ICF M-16

IAEA-25

ICF M-17

IAEA-26

Expect to be a guide.

OFE-19OF -26

CEC/ICMC

OF -27

CEC/ICMC

OF -28CEC/ICMC

OF -29Not absolutely.

P I-19M -22

P I-20

M -23

FFH -d1

Conceptual design

I I M

E CA 2011

A C2010

 The work plan was already determined at thestart‐up phase of FERP
 International conferences concerned

A C2012

P I-22

E CA 2015
A C2014

I I M

EPE

A C2016

Basic design&D

Preparations

G(Yanagi)
Large & strong magnetic field conducPreparatuctor

caled-down conductor

ductorcaled-down conductor

uctorscaled-down conductor

7

15

DesignCoil winding

rial of helical winding
High magnetic field conductor test

coil system

Manufacture of H

Electromagnetic force support structure

rial of helical winding

DesignCryostat

Manufacture of models

DesignInformation collection
from other G

After decision of theoperating magnet
temperature and summary

Common Items

Investigationgof a design
g standard

esearchc p
problem extOptimizationpand new technology
cgy studyypecifications and co eport

Bus line
Current lead
Coil power supply
Coil excitation method

I E

High magnetic field conductor test

Manufacture of models
Moderate magnetic field conductor test

DesignHigh magnetic field conductor test
rial of helical winding

Manufacture of models
Moderate magnetic field conductor test

DesignCoil winding

2010.9.24/ ev.10.7 A. agara

Moderate magnetic field conductor test

DesignCoil winding

Cooling systemeseach Project Mid- erm Plan

M -24

EPE

I I M

Budget request

G(Iwamoto)

Fusion Engineering

P I-21

E CA

EPE

eport

Basic design

Plant design

eportpecifications and co eport

Basic design

Prototypeeport

pecifications and co eport

Basic design

Prototypeeport

pecifications and co eport

Basic design

Circuit constitutio eport

I C？

Investigation

eport
ransmission of thedevice information
to other GBA

G( . anaka)

IFMIF-E IDA

Construction materials and breeder cPreparatExperiment ICF M-15

3D unit design

Draft of a designFirst wall plasma irradiation

PrepExperimentOFE-20
ICF M-15

High-strength materials neutron irradPreparat imple irradiation
Heat and hydrogen recovery

J -60 AP I-20

Improvement

OFE-21

Experiment

P I-21I FN -12

ICF M-16

Irradiation under the breeding matePreparation Irradiation of the ICF M-17
OF -27

PreparatExperiment

ICF M-16

ＳＯＦＴ-28

G( amura)
acuum vessel structure

LHD

Basic structure Details

OF -27

Plasma facing device structure

Design Manufacture and Manufacture and test of long testing materiIAEA

Device layout and evacuation

pecifications and arrange imulation

adiation loss

I AN

I FN

3D modelI FN

I C Model calculaI C ExperimeDesignG( agara)

2010
1〜3

6

2011
9 12

3

6

9 12

2012
3

6

9 12

2013
3

6

9 12

2014
3

6

9 12

2015

PC layout

Design

FFH -d1parameter

Improvement

DesignImprovemIAEA-24

３Ｄ figure

3

G(Goto)DesignBasic design

Improvement

Basic design IAEA-25

9 1

6

Building placement

econd Mid-term

Investigation

Building design

Detail investiImprovement

Concept

Improvement

Process

OFE-19I FN -10

OFE-20I FN -11

OFE-21I FN -12

As a group,

IAEA-23

ICF M-15

IAEA-24

ICF M-16

IAEA-25

ICF M-17

OF -2626

CEC/ICMC

OF -2727

CEC/ICMC

OF -2828

CEC/ICMC

Not absolutely.

P I-19M -22

P I-20

M -23

P I-21

PresentaCorrection

A C2010EPE

E CA
A C2012

I I M

eport
Conceptual design

eport

G(M. anaka)

he income and expenditure of the tritium

tudy of design

Improvem OFE-20
OFE 20tudy of calculation cEvaluation

M -24

I I M2013

est calculatDetail calculation OF -27

Estimation of an ambient dose

adiation working environment measurement Design

EPE

eport

eport
Investigation of th eport

Power generation

Estimation of the ritium environment

E CA 2011

Improvement
Improvement

eport

Correction

tart-up scenario

Expect to be a guide.

I I M

Arrangement of device
Investigation

G(Chikaraishi)

Power flow at a steady-state

E CA 2015

Manufacture

Impr

I I M2013Practical use

I FN -12G(Mitarai)

Operation scenario

A C2014EPE

IAEA-24 eport Improvement

Inve Investigation

Control parameters

Investigation

eport Improvement

afety management

Investigation

eport Improvement

Data processing

Investigation

eport Improvement

IAEA-25

eport
eport
eport
eport

G(miyazawa)

FFH -d1

Conceptual design

Basic design

eport

teady-state distribution model

Investigation

IAEA-24 eport Improvement

IAEA-25

eport

Detachment

Investigation

IAEA-24 eport Improvement

IAEA-25eport

αheating

Investigation IAEA-24 eport Improvement

IAEA-25

eport

Neoclassical transport

InvestigaIAEA-24 eport Improvement

IAEA-25

eport

IAEA-25

eport

Dynamic equilibrium

Budget request

Investigation

G( umori)&Deport Improvement

eport

NBI

Investigation

ECH

Investigation

eport Improvement

eport

ICH

Investigation

eport Improvement

eport

PelletInvestigation

eport Improvement

eport

Gas puffing

Investigation

eport Improvement

Mainstay diagnostics

Investigation

eport Improvement

Investigation

eport Improvement

Preparations
G( akamoto)G(Yanagi)
Large & strong magnetic field conducPreparat

7

ductorDesigncaled-down conductor

15

eport

G(Isobe)Moderate magnetic field conductor test

High magnetic field cond
Advanced diagnostics

2010
1〜3

6

2011
9 12

3

6

2012
9 12

3

6

eport
eport

2013
9 12

3

6

2014
9 12

3

6

2015
9 12

3

6

2016
9 12

3

6

9 12

9 / 79econd Mid-term

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (1)Superconducting Magnet GroupTask[SC Magnet]
Conductor
development
 Coil winding Cooling

Subject

Mid‐Term Goal

(International Conference: 27, Publications: 17)
Achievement

Large‐scale high‐field
conductor testing facility

 Upgrade to 15 T ‐ 680 mm Design and order of newbore, 75 kA sample current, 4 conductor testing facility‐ 50 K temp. for sample coil

CIC conductor & winding 100 kA@4.5 K, 12 T
conductor
 Design of HC with
continuous winding 100 kA@4.5 K, 12 T
conductor
 Design of HC with
continuous winding 100 kA@20 K, 15 T
conductor and joint Design of HC with jointed‐
winding

Indirect ‐cooling LTS
conductor & winding

HTS conductor & winding

EM force support structure Optimized design of robust
and minimum‐weightsupport structure[Cryogenic]

Cryogenic system Optimized design for FFHR

Cryogenic
system Coil power
supply system

Bus‐line and current‐lead Optimized design for FFHR

Coil power supply system Optimized design for FFHR

Red: Reactor Design
Green: R&D
Next Move

Collaboration

 New facility with 13 T ‐ 680
mm bore, 50 kA sample
current, 4 ‐ 50 K temp. forsample coil
Testing of JT‐60SA
 Examination of twist strain ITER
conductor/joint/model‐coil and of Nb3Sn and Nb3Al CIC
BA
ITER joint
strands
1‐D thermal analysis of CIC
 Examination of strand
Nb3Sn Rutherford‐typeconductor with Al‐alloy jacket
element for 100 kA@4.5 K,
with FSW welding
12 T (200 kA critical current)
20 kA@4.5 K, 12 T
 100 kA@ 20 K, 6 T
Tohoku Univ.
103 kA@20 K, 5.3 T with amechanically‐jointed one‐turn  Examination of fabrication
HTS coil sample
process with joint, internal
Proposal of new winding
insulation, gas coolingconcept
Design
Design with 33‐D
D FEM
 Further optimization in
calculationaccordance with660 MPa stress and further
maintenance scenario
optimization
Examination of ITER system
 Improvement of dynamic
ITER
Development of dynamic
simulator
simulator
 Design of optimized
refrigerator
Examination of ITER system Design of new HTS or MgB2 ASIPP
bus‐line for FFHR
ITER
Examination of series Design of quench
excitation of the wholeprotection system
magnet coils

10 / 79

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (2)In‐Vessel Component Group ‐1‐
Task[Blanket]Blanket systemdevelopment
 Blanket design

Subject
Radiation shield

Breeding blanket

Heat, hydrogen isotopes
recovery system

First wall

Fusion Engineering
Research Project
in NIFS

Mid‐Term Goal

Tasks for FERP (3)Task[In‐Vessel
Components]
In‐vesselpcomponent
development
 Structuraldesign Maintenance(International conference: 67, Publications: 119)
Achievement

 Property evaluation ofData of thermal conductivities
shielding materials
 Material selection for long‐ Evaluation of neutronics
term performance retention
environment Performanceenhancement Property
evaluation offf
of vanadium alloy
electron beam welding section/ Dissimilar welding test /Fabrication of Y doped high Cr
alloy Performance enhancement No performance degradationof low activation ferritic steel in 12Cr ODS at >900 oC /Fabrication of high Cr ODS
 Development of large area Multilayer oxide coating andceramic coting
nitride coating by large area
coating techniquies /Hydrogen permeation
 Acquisition of chemical
reduction:~1/200
property of coolant
Accurate evaluation ofhydrogen solubility anddiff ibilit indiffusibility
i Li‐Pb
Li Pb /
Construction of LiPb corrosion
test loop with ferritic steel
 Blanket design for FFHR‐d1
Evaluation of fuel breeding
and shielding performances by
3‐D neutronics calculation
 Data acquisition andDesign and construction ofmodeling of hydrogen
Flinak loop Orosh2i‐1
Successful circulation control
isotope transport
Development of hydrogenrecovery tube.
 Data acquisition andData acquisition of plasma
modeling of hydrogen
driven and gas driven
isotope transporthydrogen permeation.
Hydrogen retention data after

In‐Vessel Component Group ‐2‐
Subject

Mid‐Term Goal

Vacuum vessel Manufacture of a sector
mock upDivertor

 Manufacture of a divertor
moduleRemote maintenance Demonstration ofmaintenance process

Red: Reactor Design
Green: R&D
Next Move

Collaboration

 Evaluation of hightemperature stability
 Investigation of irradiation
effects
 Optimization off heat
treatment process /Irradiation test

AIST, Osaka Univ.

 Irradiation test /Comparison of 9Cr‐ODS and
12Cr‐ODS Optimization of coating
fabrication process / Coating
test on tube and duct

Tohoku Univ.
Ehime Univ.,
Hokkaido Univ.
Kyoto Univ.
Tokai Univ.
Toyama Univ.

 Understanding of hydrogentransport in LiPb flow /Acquisition of corrosion data
i LiPb flowin
fl withithtemperature gradient Investigation of heatremoval Construction of new
FLiNaK and LiPb test loops
with 3 T magnet
 Thermal recovery undermagnetic field Data acquisition of
bidirectional hydrogentransport from plasma andcoolant

Kyushu Univ.
Tokai Univ.
Kyoto Univ.

Hokkaido Univ.

11 / 79

Red: Reactor Design
Green: R&D(International conference: 67, Publications: 119)
Achievement

Next Move

Basic geometry using
numerical equations
Structure of radial build
componentAccess ports with large
aperture
R&D of a short sample madeof W and RAFM pipeExamination of specifications
and arrangements

 Optimization in accordancewith maintenance scenario

Research of maintenancecondition and machinery
Development of autonomous
mobile robot

Collaboration

 Test under high heat load

Okayama Univ. of
Science Visualization ofmaintenance scenario

JAEA
Tokai Univ.

12 / 79

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (4)Reactor System Design Group ‐1‐
Task[Design
Integration]

Subject
Task setting and project
management

Conceptual design of helicalfusion reactor[Building
Layout]Layout design andconstruction process

Reactor building design

Mid‐Term Goal

 Feedback of the result of
detailed analysis
 Cost and waste evaluation

JAEA (BA‐DDA)

 3D CAD design of reactor
building Layout design ofequipment in the building

steam turbine generator
 Estimation of power flow
and design of start up
procedureTransmission and hydrogenproduction

 Integration design ofhydrogen production plant

Reactor System Design Group ‐2‐[Tritium]

Tritium fuel balance

Tritium safety handling

Tritium decontamination

Tritium monitoring[Operation
Control]Estimation of the floor space
Evaluation of leakage field
profileSafety analysis and control
systemBurn control

Mid‐Term Goal

 Determine the location ofbuildings
 Estimation of the amountof time of each task

Osaka Univ.
Conceptual design based on Adjustment of thermal
steam turbine generator
source and heat exchanger Tokai Univ.
designMeiji Univ.
Conceptual design of start up
scenario and dc power system  Feed back of the design
results of other componentsof SC coils
Conceptual design ofhydrogen production was
published Conceptual design of hybrid
energy transmission line waspublished

Tasks for FERP (5)Subject

Collaboration
JAEA (BA‐DDA)
Universities

 Development of MgB2
cable for SC transmission
line

Task

Next Move Collaboration with IFERC
 Operation of large R&D
devices equipped by the
supplementary budget

systemFusion Engineering
Research Project
in NIFS(International conference: 56, Publications: 81)
Achievement

 Publish a conceptual design Interim report on FFHR‐d1
report of helical reactor
conceptual design was
FFHR‐d1
published Planning of real‐scale andManaged a large
real‐environment test
supplementary budget
 Establishment of consistent Development of systemand feasible design concept
design code
Basic 3‐D shape design of in‐vessel components
 Site layout design
Listing of buildings
 Establishment of concept
Listing of necessary task atof construction process
the construction[Power Supply] Generator and power supply  Design report based on Power supply
 Generator

Red: Reactor Design
Green: R&D

 Component design ofhydrogen production plant Development of MgB2
cable with high current
capacity

ASIPP

13 / 79

Red: Reactor Design
Green: R&D(International conference: 56, Publications: 81)
Achievement

Next Move

Collaboration

 Estimation of tritium
Demonstration of tritium fuel  Consideration and proposal
inventory, particle balanceof advanced tritiumbalance using simple mass
and required tritium
processing system based onbalance model and estimation
decontamination factor [DF] of required throughput and DF, the fuel balance modeletc
 Development of highDemonstration of preliminary  Verification and validation Akita Univ.
throughput (> 1000 m3/h)
integrated tritium removalof integrated tritium
Nagoya Univ.
tritium removal system andsystem code combined withremoval system code using
its system code
catalyst and membrane
middle scale tritium removal
separator
systemClarification of tritium
decontamination in/on themetal materials

 Development of simple
Univ. of Toyama
tritium decontamination(HRC)
system by atmosphericpressure plasma
 Tritium measurement and Kyoto Univ. (RIC)
Nagoya Univ.
demonstration of 2x10‐4
Bq/cm3
 Shorter counting time
toward 6 Bq/cm3‐water@10 minReview of safety analysis
 Preparation of safetyConsideration of safer blanket analysis code
designDemonstration of ignition‐
 Detailed physics analysis on Tokai Univ.
access by quasi‐1D calculation
the simulated profiles

Understanding of hydrogenisotope behaviors in/on astainless steel by glow
discharge cleaning
 Demonstration of low level Tritium gas: performancetritium monitoring :optimization
Tritiated water : few Bq/cm3
2x10‐4 Bq/cm3‐gas
3@ 180 min.
6 Bq/cm ‐water @10 min.

 Conduct safety analysis
 Conceptual design ofcontrol system
 Establishment of plasma
operation scenario

14 / 79

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (6)Reactor System Design Group ‐3‐
Task[Core Plasma]

Subject
Plasma experiment

MHD equilibrium andstability

Neoclassical transport

Mid‐Term Goal

Red: Reactor Design
Green: R&D(International conference: 56, Publications: 81)
Achievement

 Obtain the radial profile
data extrapolatable to thereactor w/o enhancing Self‐ignition in FFHR‐d1A with
Pfusion ~ 3 GW @ f ~ 3 (0 ~10 %)Sub‐ignition in FFHR‐d1B with
Q ~ 20 @ f = 1 (0 ~ 2.4 % andPaux ~ 30 MW) Mitigation of the Shafranov HINT2 and VMEC have beenshift at high‐beta
applied Definition of the beta limit High‐aspect ratio and Bv
control are effectiveConfinement is not largely
deteriorated at DI ~ 0.2
 Evaluation of theFORTEC‐3D and GSRAKE
neoclassical transport
have been applied
Neoclassical thermal loss canbe compatible with  heating

Next Move

Collaboration

LHD Sub‐ignition in FFHR‐d1B
with Q > 30 @ f =1
 Exploration of the better
magnetic configuration (e.g.,
vertical elongation at c =1.20)
 Analysis of the profiles
LHD
during the start‐up and
NSRP
sustainment phases
predicted by HELIOSCOPE

 (same as above)

LHD
NSRP

Alpha heating

 Evaluation of the direct loss GNET and MORH have been
and the heating power ofapplied Direct loss of particles can be ~15 %, or lessalpha particles

 (same as above)

Kyoto Univ.
LHD
NSRP

Anomalous transport

 Evaluation of theanomalous transport
 Development of 1D coreplasma simulation code
 Establishment of theplasma operation scenario Find out the detachment
scenario (same as above)

NSRP

 Integration of TASK‐3Da
into HELIPSCOPE

LHD
NSRP

Plasma operation scenario

Application of GKV‐X isconsideredNGS and DPE are included to
HELIOSCOPE
Self‐ and sub‐ignition
scenarios in FFHR‐d1B aredevelopedDetachment exp. in LHD

15 / 79

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (7)Reactor System Design Group ‐4‐
Task[PlasmaHeating]

Subject
NBI

ECH

ICRF

[Fueling]

PelletMid‐Term Goal

(International conference: 56, Publications: 81)
Achievement

Fundamental experiment on 6.9 MW@ 190 KeV for 1.5 sec.
photo‐neutralizer
per NBI Design of 1.5‐2.0 MeV
more than 16 MW injection
beam accelerator
with 3 beamlines Design of neutron shield4 MW for 10 sec. pulse
 Demonstration of 1 MW 60 0.4 MW 20 minutes achieved
minutes injection
16 % OXB heating efficiency
 Demonstration of high@77 GHzefficiency OXB heating
Ray tracing environment in Find high efficiency OXB in
FFHR established
FFHR
 Development of fast wave Cold plasma model with threesimulation‐framework withdimensional calculation
actual geometrical model Optimization of pellet
injection condition taking
into account ablation andplasmoid homogenization

Red: Reactor Design
Green: R&D
Next Move

Collaboration

 Production of perfect ion‐
ion plasma including lessthan 1/1000 of electron / H‐ion ratio Beam trajectory simulation
 1MW 20 minutes
 High OXB heating
efficiency @154 GHz
 Ray tracing with mode
conversion in FFHR

JAEA,
RFX Group (Padova,
Italy),
Tohoku Univ.
Keio Univ.
Univ. of Tsukuba
Kyoto Univ.
Kyushu Univ.

 Antenna with Faradayshield and protector
 Hot plasma modelTokyo Univ.
MITModeling completed based on  Exploration of thethe experimental results inpossibility for the very highLHD
speed pellet injection
beyond 10 km/s

16 / 79

Fusion Engineering
Research Project
in NIFS

Tasks for FERP (8)Reactor System Design Group ‐5‐
Task[Diagnostics]

Subject

Mid‐Term Goal

Neutron diagnostics

 Selection of diagnostics
 Put diagnostic devices in
CAD
 Design of the device

Spectroscopic diagnostics

 Design of the device

Investigation of available
diagnostics

Interferometer / reflectmeter  Design of the device
 Demonstration of high‐resolution measurement at
high‐density in LHD
Thomson scattering Design of the LIDAR
system.

Red: Reactor Design
Green: R&D(International conference: 56, Publications: 81)
Achievement

Next Move

Collaboration

Initial consideration results
submitted to PFR Arrangement of diagnostic Tokyo Institute of
ports
Tech.
JAEA
Feasibility check of existing Survey of diagnostic port
Nagoya Univ.
available for neutron
neutron flux monitor andspectrometer for DEMO
diagnostics
Particle source profile Spatial profile
Kyoto Univ.
measurement with single line‐
measurement of impurity
Shinshu Univ.
of‐sight
lines in EUV range
 Bench tests of a shorter
Kyushu Univ.
Measurement test with awavelength (Nd:YAG laser) Shimane Univ.
proto‐type (CO2 laser) system
has begun on LHD
systemChubu Univ.
Feasibility check on the high‐power laser for LIDAR

 R&D on the high‐power
laser

Osaka Univ.
Institute for
Molecular Science

17 / 79

Fusion Engineering
Research Project
in NIFS(1‐2) Organization of FERP FERP consists of 13 task groups and 44 subtask groups Leaders meeting (Exec. Dir.+ 2 Div. Dir. + 13 TG leaders) Project meeting (Researchers from NIFS and ex‐NIFS)

18 / 79

Fusion Engineering
Research Project
in NIFS(1‐2) Organization of FERP FERP consists of 13 task groups and 44 subtask groups Leaders meeting (Exec. Dir.+ 2 Div. Dir. + 13 TG leaders) Project meeting (Researchers from NIFS and ex‐NIFS)

Young Researchers
are nominated as the
TG leaders!

19 / 79

Fusion Engineering
Research Project
in NIFS(1‐2) Organization of FERPSC Magnet

 FERP consists of 13 taskBuilding
groups and 44 subtask groups
Cryogenics
 Leaders meeting (Exec.layout
Dir.+ 2 Div. Dir. + 13 TG leaders) Project meeting (Researchers from NIFS and ex‐NIFS)
SC
magnetTritium

OperationOicontrol

Designintegration

Tritium /SafetyBlanketPower‐supply

FusionReactorConceptual
DesignDiagnostics

High Heat/Particle
Load
Handling

In‐vessel
components

Young Researchers
are nominated as the
TG leaders!

Low‐
Activation
Materials

BlanketCore plasma

Fuelling
Plasma heating

20 / 79

Fusion Engineering
Research Project
in NIFS

Any Researcher Can Participate in FERP
Across the Department of Helical Plasma Research

From the FY2010, 4
projects have started in the
new organization for the
2nd Mid
Mid-term
term goal & plan
Fusion Engineering Research
Projectwith about 60 staffs,
mainly based on the 2 divisions:
Device Engineering and Advanced
Physics Research Division (Staffs:
7,7,4 )
LHD maintenance and D-D safety devices
Trace tritium monitoring and handlingLarge SC magnet system and applications

Fusion System Research Division(Staffs: 6,5,8)
Helical reactor DEMO design
Remote maintenance and replacement
Low activation mater. and long-life liq.
blanketPWI and high-heat flux components
Atomic and molecular processes

21 / 79

Fusion Engineering
Research Project
in NIFS

Relations to Other Groups
Network for promotion of engineering researchInstitute for Materials Research : HFLSM, Tohoku University
Research Institute of Superconductor Science and Systems, Kyushu University
Tokyo Institute of Technology, Osaka Univ., Kyoto Univ., Seikei Univ., Toyohashi Univ. of tech., Tokai Univ., Kagoshima Univ., Japan Atomic Energy Agency, etc.

Hydrogen Isotope research Center, University of Toyama,
Radiochemistry Research Laboratory, Shizuoka University
Hokkaido Univ., Akita Univ., Ibaraki Univ., Univ. of Toyama,
Shizuoka Univ., Nagoya Univ., Kumamoto Univ., Kyushu Univ.,
Japan Atomic Energy Agency, etc.

Institute of Engineering Innovation, School of Engineering,
University of Tokyo
Institute of Advanced Energy, Kyoto University
Tohoku Univ., Tokyo Institute of Technology,
Osaka Univ., Ibaraki univ., Univ. of Toyama,
Univ. of Fukui, Kyushu Univ.,
Japan Atomic Energy Agency, etc.

Institute for Materials Research, Tohoku University
Institute of Advanced Energy, Kyoto University

Plasma Research Center, University of Tsukuba
Graduate School of Engineering, Osaka University
Hokkaido Univ., Tohoku Univ., Shizuoka Univ.,
Kyoto Univ. Shimane Univ., Kyushu Univ.,
Japan Atomic Energy Agency, etc.

Fusion Reactor

Hokkaido Univ., Muroran Institute of Technology,
Hachinohe Institute of Technology, Ehime Univ.,
Hiroshima Univ., Univ. of Fukui, Osaka Univ.,
Kyushu Univ., Japan Atomic Energy Agency, etc.

22 / 79

Fusion Engineering
Research Project
in NIFS

Tritium Science and Technology
Hokkaido
Univ.
Tritium
Material Int.

Akita Univ.
Tritium
Safe
process

Hydrogen isotope
separator“NIFS-PSA ”

Ibaraki Univ.
Radiation
Biologicaleffects

General joint research(Kyushu Univ.)

ToyamaUniv.
Tritium
Material Int.

NIFS
・Promotion of joint research・Adjustment of network
・Mutual use of research facilities

Shizuoka
Univ.
Tritium
Material Int.

Tritium plasma exposure /Plasma decontamination
evaluation device（Univ. of Toyama: HIRC）
Interactive joint research

Univ. of OEH
Tritium
Biologicaleffects

Nagoya Univ.
Isotope sep.
Fuel recovery
Kyushu Univ.
Tritium
Environmental
fate

Tritium recovery equipment（NIFS, Nagoya Univ.）
General joint research(Nagoya Univ.)

Fusion Engineering
Research Project
in NIFS

Different chemical forms
Tritium recovery equipment（NIFS, Kyushu Univ）

Fuel cycle simulation testing
equipment “EXPRESS”（Shizuoka Univ.: R.R. Lab.）
LHD plan joint research

23 / 79(1‐3) Research Environment
Devices for engineering research in NIFS since 1989

Year

The main fusion engineering research equipment in NIFS

1989
1990
1995
1997

Fatigue testing equipment was introduced

1998

Scanning electron microscope was introduced

1999

30 kg Vanadium ingot (NIFS‐HEAT‐1) production

2000

170 kg Vanadium ingot (NIFS‐HEAT‐2) production

2001

X‐ray photoelectron spectrometer was introduced

2002

Osaka Univ.：Powerful neutron source lithium target test facility

2005

Creep testing machine (Unit 1) was introduced

2006

X‐ray diffractometer was introduced

2007
2008

Creep testing machine (Unit 2) was introduced
Liquid lithium loop production and operation

2012

2013

LHD first plasma
Fusion Engineering ResearchCenter established

External evaluation onengineering research

2009

2010
2011

EventsNIFS established

Surface analysis and testing equipment (SUT) and Active Cooling Test‐stand (ACT) were introduced
Large superconducting test facility was introduced
Micro‐hardness tester was introduced

Creep testing machine (Unit 3) was introduced
Production of particle dispersion strengthened vanadium alloy
Field emission scanning electron microscope was introduced
Molten salt loop (Orosh2i‐1) production and operation
Variable temperature low temperature equipment (Supercritical helium generator etc. update）
Conductor magnet test facility （Including variable temperature current lead）
Heat and mass flow loop equipment (Orosh2i‐2)
Transmission electron microscope （TEM)
Ultra‐high vacuum creep testing machine
Bond testing equipment （HIP, Ball mill etc.）
Active Cooling Test‐stand (ACT‐2)
Hydrogen accumulation analyzer （Pelletron Accelerator Surface Analyzer and SEM）
ＬＨＤ irradiation testing equipment （Focused ion beam system, TDS etc.）
Hydrogen testing and measurement equipment （Gas composition analyzer, FTIR, etc.）
Electron beam processing machine

FERP launched
Large supplementarybudget secured

External evaluation

24 / 79

Fusion Engineering
Research Project
in NIFS(1‐3) Research Environment
R&D onIndirect ‐Cooling LTS
Conductor

R&D on CIC
Conductor

FE‐SEM
15 T SC Magnet
Test Facility

H2 Permeation Test
Stand

(under construction)

XRD
Glove‐Box (for MA)“VEHICLE ” for“VEHICLE‐1”f
PWI R&D

FLiNaK Loop

“Orosh2i‐1”
TDS
XPS

Liquid Breeder
Test Stand

JT‐60SA Model CoilTest

R&D on HTS
conductor

Arc Furnace

Glove‐Box

Fusion Engineering
Research Project
in NIFS

25 / 79

Large Supplementary Budget of
2.4 Billion JPY in FY2012(1) SC Magnet‐ 13 T SC magnett test
t t ffacility,
ilit ...

(2) Blanket‐ Twin loop with 3T SC magnet, ...

(3) Low‐Activation Material‐ HIP device, TEM, creep test device, ...

(4) Divertor‐ High heat load test device of 10 MW/m2, pelletron tandem acceleratorof 1 MV, ...

(5) Tritium‐ Gas / liquid analyzer, …

26 / 79

Fusion Engineering
Research Project
in NIFS

15 T SC Magnet Facility
R&D by SC magnet TG

The superconductor testing facility at “Superconducting Magnet Systems Research Laboratory” will be upgraded(after 25 years operation) to increase the bias magnetic field from 9 T to 15 T so that 100 kA‐class conductor
samples will be tested at temperature 4 – 50 K
3. Temperature‐variablecurrent leads

50 mm

World’s Highest B in
a 700 mm Bore

Coil sample with100 kA‐class superconductor

twisting

1. Outer coil
2. Inner coil

Fusion Engineering
Research Project
in NIFS

700 mmbending
27 / 79

Twin Loops with 3T SC Magnet
R&D by Blanket TG
World’s Highest B⊥

Orosh2i‐2
EM
pump
p
p

Cooler

LiPb

FLiNaK Mechanical~5 m‐ Operational Recovery Of Seperated
Hydrogen and Heat Inquiry‐ Forced circulation loops of FLiNaK(~500 ℃) and LiPb (~300 ℃)‐ Integrated test stand with a SC magnetof 3 T

Coolerpump

SC magnet

Test
sections

3T
HeaterHeater

1.5
m/s
28

~10 m
Basic configuration of Orosh2i‐2Specifications of Orosh2i‐2・Pipe diameter： 1 inch
・Normal operation temp.： FLiNaK 500℃, LiPb 300℃
・Maximum flow velocity： ~1.5 m/s ・Inventory： ~100 L
・Magnetic field： max. ~3 T（CS magnet）, 50 cm Φｘ 15 cm

Simulation of temperature and flow velocity in fusion blanket
Integrated tests of MHD pressure drop, control of laminar and turbulence flow, hydrogenand heat recovery, corrosion behavior etc. under intense magnet field.
Test stand for elemental technologies developed in collaborative studies.
28 / 79

Fusion Engineering
Research Project
in NIFSHIP Device, TEM, Creep Test
R&D on low-activation materials by Blanket TG

Nano‐particle
dispersion
strengthenedmaterials

Mechanical
Alloying

Surface morphology and composition Field Emission SEM（existing）

Characterization of nano‐particle dispersion

Raw Powder Planetary ball millingEvaluation of hightemperature strength andlow temperature ductility

 TEM
 EDS

HIP

5 mm

50 mm

(Hot Isostatic Press)

MiniaturesizeStandardsize

 High temperatureisostatic sintering andjoining test system（Fabrication of medium
size test pieces）

Fusion Engineering
Research Project
in NIFS High temperature creep test
facility High speed impact test
facility

Target （non‐irradiation）
Yield stress：
300 MPaMP <Thermal creep：< 1 % at 100 khr
DBTT：
< RT

Establishing fabrication
technology
29 / 79High Heat Load Test Device
R&D by In-Vessel Components TG

ACT‐2‐ Ultra high heat flux test stand‐ 10 MW/m2 of heat loading by 300 kW electron gun‐ Large vacuum vessel‐ R&D on material, cooling media, and bonding technique‐ Realistic scale components

300 kW electron gun

Schematic of ACT‐2
30 / 79

Fusion Engineering
Research Project
in NIFS

Accelerator for Material Test
R&D by In-Vessel Components and Blanket TGs

Non‐destructive analysis‐ By 1 MV pelletron tandem accelerator‐ Quantification of the retained H‐ Multiple analysis of RBS, ERD, NRA, and
PIXE

1 MV tandem accelerator③NRANa(Tl)

4He
RBS

=18 deg.
2.8MeV‐ 4He2+
etc.

①RBSSSDCountsQuantitative analysis ofdeposition element
5000
4000
3000
2000
1000
00

RBS

SMo

HSi
100

Fusion Engineering
Research Project
in NIFS

200 300 400 500
Channel Number

X‐ray

Depth profile of H isotopes
=12 deg.
HERD④PIXESDD
High resolution(ppm) element
analysis600②ERDSSD
Quantitative analysis of
the plasma particles
Count

‐ray
Sample Material

80
60
40
20
00

ERD
SH
100
200
300
400
Channel Number

500

31 / 79

Advanced fuel cycle system
R&D by Tritium TG

Proposal of asimplified fuelc cle systemcycle
s stem‐ toward low tritium
inventory

Feasibility
F
ibilit studies
t di off a llow
temperature processing

ProposalPl off tritiatedt iti t d watertprocessing

Fuel purification processing by
three stage cryogenic
condensation system

Tritiated water processing by
dual temperature and dualpressure type CECE system[Supported by Dr. Iwamoto (NIFS)][Nagoya Univ., Dr. Sugiyama]

Hydrogen isotope separation bycryogenic pressure swing
absorption system

Highly tritiated water processing by
gas phase processing system[Kyushu Univ., Dr. Kotoh][Univ. of Toyama, bidirectional Collab.]

Support by gas and liquid analyzers
Advanced gas phase
tritium analyzer

Advanced tritiatedwater analyzer(Proportional counter with apulse shape discriminator)[Nagoya Univ., Kyoto Univ.](Solid scintillator type)[OHYO KOKEN KOGYO CO.,LTD]

Stable Isotope analyzer

Gas chromatograph/mass spectrometer(FTIR spectrometer,
Gas / liquid / solid surface)(Analyzer in operation)

32 / 79

Summary of [1] Development of Research System andEnvironment [1] 研究環境の整備

Fusion Engineering
Research Project
in NIFS

Points of Evaluation

Facts
The target of FERP (“Promotion of conceptual and baseline

Whether or not the target of FERP,
pp p
1‐1 initiated in FY2010,, is appropriate

平成２２年度にプロジェクトとして位置付けられた核融合⼯学研究プロジェクトの⽬標設定は適切か

designs toward realization of a steady‐state helical fusion
reactor and construction of engineering basis that enables
real
scale and realenvironment R&D
real‐scale
real‐environmentR&D”) is appropriate:
 FERP has successfully launched as the PROJECT of NIFS Roadmap and tasks to do are defined with five
fundamental R&Ds

The organization of FERP coincide with the target andproperly functioning:

Whether or not the organization of FERP  13 TGs are organized based on the tasks defined by theis coincident with its target and properly target
1‐2 The leaders meeting is properly leading the projectfunctioning?
推進体制は⽬標に合致し 適切に機能しているか
推進体制は⽬標に合致し、適切に機能しているか The pproject
j meetingg of more than 770 times has been held Collaborations with other groups are being carried out
successfully

Whether or not an appropriate research The research environment in NIFS is being provided
appropriately:
environment is provided for the Five fundamental R&Ds are going on successfully
1‐3 establishment of academic
 Collaborations with other groups are being carried out
fundamentals
successfully
⼯学基盤の構築を可能とする研究環境の整備は適切に進められているか The research environment is now widely improving withthe large supplementary budget in FY2012

33 / 79[2] Research Achievements

Fusion Engineering
Research Project
in NIFS~ Whether or not FERP is achieving internationally evaluatedresults throughout the study on helical fusion reactor
研究成果 〜ヘリカル型核融合炉の研究を進めることにより、国際的に⾼いレベルの成果を上げているか(2‐1) Helical fusion reactor design
ヘリカル型核融合炉の設計(2‐2) R&D toward establishment of the engineering basis
⼯学基盤構築に向けた研究

34 / 79(2‐1) Helical Fusion Reactor Design

Fusion Engineering
Research Project
in NIFS

FFHR2m2

Core plasma TG

In‐vessel
components TG

Radial profiles

Radial build
DesignIntegration TG
Design window

Blanket TG

Blanket TG

Neutronics (TBR)

3D blanket designCore plasmaClTG
Direct Profile
Extrapolation

3D neutronics
Superconducting
coil TG
Cooling capability

LHD project
Experiment

Superconductin
Designg coil TG

Integration TG
Cooling capability

Consistency check

In‐vessel
components TG

Numerical model

Divertor design

Num. Sim. Res.
project
Physics analysis

Pumping

35 / 79

1st Round

Fusion Engineering
Research Project
in NIFS

FFHR-d1 design parameters are determined

3 Determine the radial build byExtrapolation from LHD (#96164, t = 6.966s)
to FFHR-d1 (B = 5.09 T, R = 14.4 m)

50
40
30
20
10
0
10

ax

ne

ax

taking into account the shrinkage
of cooled devices

f = 2.80

Reactor

n

n

Sudo

c

LHD

Te

f = 6.60

Reactor

T

5

LHD

0

eng

5

4 TBR estimation by

f = 5.40

Reactor10

neutronics calculationof the breed and shieldblankets

LHD

02= 1.26

P '

DPE

1

P '
B

0
1000
500

P -P
P

B

P

loss

P

0
1

(P

/P

dep



B

)

dep1 avg= 0.720

0.5
P

dep

/P

LHD: 0.536
dep1

0
-1

-0.5

0

0.5

1

5 Cooling simulation of SC helical

1 Estimate radial
profiles in FFHR-d1 by
extrapolating the profile
data obtained in LHD(DPE: Direct Profile
Extrapolation)coils to determine the tolerable
nuclear heating

2 Identify the design window by an
integration code HELIOSCOPE

36 / 79

Fusion Engineering
Research Project
in NIFS

Design Parameters of FFHR‐d1

ISFNT
2011

A. Sagara et al., Fusion Eng. Des. 87, 594 (2012)

GW(on average)

37 / 79

Fusion Engineering
Research Project
in NIFS

2nd Round

Fast neutron flux (>0.1 MeV)

Position Y

Blanket TG
3D blanket design

Numerical model

OV coil

2.154E+14

2.154E+13

IV
1E+13
coil
1.000E+13

Flibe+Be/FS
breeding
blanket
FS+B4Cshield

4.642E+12
2.154E+12

Helicalcoil

1.000E+121E+124.642E+11
2.154E+11
1.000E+111E+114.642E+10
2.154E+10
1.000E+10

1E+10

Core
plasmaHelicalcoil

4.642E+09
2.154E+09
1.000E+09

1E+94.642E+08

Neutronsource1E+82.154E+08
1.000E+08

Position X

In‐vessel
components TG

4.642E+13

Divertor
Pumping
port

Blanket andshield A

Blanketandshield B
Helicalcoil

3D neutronics

Cooling capability
Consistency
check

1E+15

4.642E+14

WC
shield1E+141.000E+14

Design of in-vessel components

Superconducting
Design IntegrationTG
coil TG

1.000E+15

Blanket andshield B

Pumping port(n/cm2/s)

Estimation of the neutron flux distribution by the3D simulation code MCNP 【Blanket TG】

Divertor design
Pumping~8m

Design of the pumping ducts torealize a high-conductance 【Invessel components TG】

~2m

~8m
~0.5m

~2m
~4m
Numerical modeling of the blanket poloidal shape being
consistent with plasma and divertor legs at arbitrary toroidal
angle  【Design integration TG】~12m

Bottom port
38 / 79

Fusion Engineering
Research Project
in NIFS

Structural Analysis with 3D‐CAD
Large maintenance ports are applicable with tolerable EM stress

Upper port
(6 m x 10 m x 11 m)

ISFNT
2013

Outer port(bottom 8.5 m x height 7.5 m)

Rc = 15.6 m, Bc = 4.7 T, Pfusion ~ 3 GW

Numerical modeling of in‐vessel components‐ Make modification of the design andtranslation between CAD softs easy

3D structural analysis‐ Von Mises stress < 660 MPa with 250 mm thickhelical coil case

Maintenance scenario

Results of structural analysis‐ Parallel maintenance from large 10 ports

Fusion Engineering
Research Project
in NIFS

3D Neutronics Analysis

39 / 79

ISFNT
2013

Neutron flux can be reduced at divertor set behind the blanket
Fast neutron flux (>0.1 MeV) (n/cm2/s)

BlanketandshieldBshieldDivertor
Pumping
port
Helicalcoil

Blanket andshieldFast neutron flux (>0.1 MeV)
Poloidal
coil

1E+15
1E+14
1E+13
1E+12

Core
plasmaDivertor
space

Poloidalcoil
Helicalcoil
Inboardblanketspace:
70 cm

3‐D neutronics calculation model
keeping consistency with core plasma,magnet, in‐vessel component designs.

Divertor space

1E+9

Divertor
Pumping
port

1E+15
1E+14
1E+13
1E+12
1E+11

1E+11

Divertor
space

1E+10

Helicalcoil

HelicalcoilCoreplasma(n/cm2/s)

Flibe blanket+ WC shield

Flibe blanket+ (Ferritic steel+B4C) shield

1E+10
1E+9

Fast neutron flux distribution calculated by MCNP code D neutronics
3‐D
t i analysis
l i‐ Sufficient radiation shielding and tritium breeding (TBR: ~1.08) performances of the FLiBe blanket
have been shown by MCNP
‐ Irradiation damages on divertors set behind the radiation shield will be ~1/10 (1.0‐1.6 dpa/y) at
inboard and ~1/100 (0.06 dpa/y) at outboard compared with those at the first wall
‐ Possibility of applying copper alloy for divertor cooling emerges
40 / 79

Fusion Engineering
Research Project
in NIFSInter‐Project Collaboration

IAEA
FEC
2012

With the LHD project and the Numerical Simulation Research Project

1 Proposal of experiments in LHD using the similar magnetic

1
14.0 m, vessel

configurations as FFHR-d1

ratio off confined alpha14.4 m, vesselCore plasma TG
Direct Profile
Extrapolation

IV

IS

OV

0.8

14.0 m, LCFS

0.6

14.4 m, LCFS

0.4
0.2
0

The number of poloidal coils is
reduced from 6 in LHD to 4 in FFHR‐
d1 to secure large maintenanceports

Experiment

3 Identification of the
MHD equilibrium in
FFHR-d1 using HINT2and VMEC
Magnetic surfaces are destructed
at high‐beta (left) can berestoration by the plasma
position control (right) 【HINT2】

Shafranov shift is mitigated in the high aspect ratio
configuration (red and magenta) compared with thestandard configuration (blue)

0.4

0.6



0.8

1

4 Detailed physics analysis

Physics analysis

estimation of the radial
profilesfil iin FFHR
FFHR-d1
d1 b
by
DPE (Direct Profile
Extrapolation)

0.2

Both of the alpha re‐entering effect andthe plasma position control is effective to
reduce the alpha loss 【MORH】

Num. Sim. Res.
project

2 Plasma experiment andFusion Engineering
Research Project
in NIFS0

LHD project

VacuumVacuum0 ~ 8.5 %0 ~ 10 %41 / 79

Operation Scenario is Being EstablishedQuasi 1D plasma simulation‐ Profile effect is taken into account based on NGS(Neutral Gas Shielding model) and DPE (Direct
Profile Extrapolation method)

ISFNT
2013

Detailed physics analyses‐ Shafranov shift mitigation is possible‐ Neoclassical loss and alpha loss are tolerable

IAEA
FEC
2012

0 .6

w/ Bv

Results of core plasma simulation





- P

B

0 .3
Q
0 .2

neo
i

n eo
e

S

S
P

B

0
0

0 .2

0 .4



0 .6

0 .8

1

Neoclassical thermal loss iscompatible with the  heating
1

lost

0 .8

confined

0 .6
0 .4
0 .2

Ratio of confined alpha0

Magnetic surfaces similar to
those in vacuum are obtained athigh beta by applying Bv

P

S

Q

ratio of confined alphaTe0 ~ 8.5 %

neo
to t

0 .1

0 ~ 7.5 %w/o Bv

(c)

Q

0 .4

tot

Q

vacuum
(b)

P

0 .5

neo

ne

0 = 0 %S (GW)

(a)

0

0 .2

0 .4



0 .6

0 .8

1

Direct loss of alpha particles istolerable
42 / 79

Fusion Engineering
Research Project
in NIFS(2‐2) R&D
Five fundamental engineering studies are ongoing

SC Magnet
R&D on three kinds of SC Magnet‐ Demonstration of 100 kA in HTS coil

BlanketTritium / Safety

R&D on elemental
technologies for liquid blanket

R&D on hydrogen isotope
processing

Collaboration withLHD
 FFHR configuration
 Material test
 EBW
 Hydrogen isotope
processing Neutron diagnostics‐ Demonstration of FLiNaK
circulation in Orosh2i‐1

Low Activation Materials
Low‐Activation

High Heat / Particle
Load Handling‐ Improved characteristics of V‐alloy at ~700 °C

R&D on the divertor device‐ Double layer ceramic coating

R&D on V‐alloy and coating‐ Bonding of W and Cu / RAFM
‐ Detachment exp. In LHD
43 / 79

Fusion Engineering
Research Project
in NIFS

R&D on SC Magnet
Three types of SC conductor have been developed
CIC Conductor Testing

Joint

1410

High-Temperature Superconductor

 High‐Temperature Superconductor (HTS) with GdBCO has
achieved 100kA@20@ K,, 5 T and 120 kA@4.2@4 K,, 0.4
4T Mechanical lap‐joint developed by Tohoku Univ. has satisfied
required joint resistance Short‐sample conductors and CS model
coil were tested for JT‐60SA
 Conductor
Cond ctor joint test is being carried ooutt
for ITER‐TF

Indirectly‐cooled Nb3Sn conductor
Indirectly‐cooled Nb3Sn conductor with Rutherford cable andAl‐alloy jacket with Friction Stir Welding is being developed5 kA@12 T‐class sample was tested as a three‐turn coil
20 kA@12 T‐class & 100 kA@12 T‐class samples were fabricated44 / 79

Progress in the HTS Option of Helical Coils

Fusion Engineering
Research Project
in NIFSHTS: High Temperature Superconductor
Joint‐ High cryogenic stability (no worry of quench)‐ High mechanical strength with YBCO

Segmented‐fabrication (jointed‐
winding) of helical coils
Helical Coils‐ Accelerate the manufacturing process‐ No need of large winding machine

R&D on the jointed HTS coil
‐ One turn HTS coil sample with a mechanical joint‐ 100 kA coil current has been achieved @20 K, 5 T

45 / 79

Fusion Engineering
Research Project
in NIFS

R&D on Blanket

VEHICLE‐1
for PWI
experimentPartial Pressure (Pa)Elemental technologies for liquid blanket have been developed
He
HeプラズマplasmaH
plasmaData acquisition of plasma drivenhydrogen permeation through F82H at
520 oC

Control panel

Completion of construction of FLiNaK loop
Orosh2i‐1 and start of operation.

H2 pressure
P1-7a) Hydrogen

3 10

-7

He plasma 予 照射 後にH 2 plasma

2 10

-7

1 10

-7

H 2 +He混合ガス plasma0100

H 2 plasma

200
300
400
Temperature (℃)

500

600

1.5 10

-7

1 10

-7

He plasma

5 10

-8

He plasma 予照射後にH 2 plasmab) Helium

H 2 + He混合ガス plasma
0

0

100

200
300
400
Temperature (℃)

500

600

Analysis of hydrogen
retention in F82H after He
plasma pre‐irradiation

Releasedgas
analyzer
QMS output (a.u.)

FLiNak loop

-7

4 10

0

Partial Pressure (Paa)

F82H試料
sample5 10

H2 pressure P2

Permeation n2
Permeation
n1

Time

Development of electrically insulated hydrogenrecovery unit for molten salt coolant
46 / 79

Fusion Engineering
Research Project
in NIFS

FLiNaK Circulation

Extension
延長シャフトshaft
インペラー
Impeller（回転羽根）

Experiment in Orosh2i-1
遠心
Motor
ポンプ

FLiNaK loop

溶融塩液面
LiquidFLiNaK(transparent)（無色透明）

Extension
延長
shaft
シャフト
(50cm)
Dump tank

Loop tube
ループ
配管

Development ofcentrifugal pump forhigh temperaturemolten salt loop

Operational Recovery Of Separated
Hydrogen and Heat Inquiry

Time (s)Successful control of FLiNaK circulation andvelocity measurement at 500 oC

・Pipe diameter： 1/2 inch
・Maximum temperature： 600 °C
・Maximum flow velocity： ~0.5 m/s
・Inventory： ~3 L

‐ Operation of centrifugal pump for high temperaturemolten salt has been demonstrated

Development and experience accumulation on

The world’s first integrated molten salt
loop system for study of separate recovery
of hydrogen and heat

Fusion Engineering
Research Project
in NIFS

Velocity
(m/s)

インペラー
Impeller

Rotation(rpm)

Console box‐ Circulation control of high temp. molten salt
‐ Velocity measurement‐ Hydrogen charge and recovery‐ Handling of molten salt etc.

47 / 79

R&D on Vanadium Alloys and Ceramic CoatingV‐alloys are promising low
activation structural material

Ceramic coating is essential tobreeding blankets
ICFRM‐ Microstructural control => high‐T strength ‐ Mechanical‐alloying
y g and HIP => both strength
g andelongation 

2013‐ For electrical insulation, and‐ Reduction of the tritium permeation‐ Double layer Er2O3 coating technique on the
tube interior has been developed
Deposition area: 500mm

Before coating

After coating

200nm
Annealed(Standard)

200nm

100nm

Cold‐worked andaged

Mechanically‐
alloyed and HIPed

Er2O3 coating on
the tube interior
Depo

Mechanically‐alloyed and HIPed
Cold‐worked and aged
Annealed

Er2O3

V‐4Cr‐4Ti
ICFRM
2013

Microstructure and tensile properties of standard andstrengthened V‐4Cr‐4Ti

CeO2
SUS316200 nmCross section of the double‐layer coating

48 / 79

Fusion Engineering
Research Project
in NIFS

R&D and Related Researches on Divertor
Bonding of tungsten
with other metals

Divertor detachment forheat load reduction‐ Brazing of tungsten mono‐block with copper alloy
tube‐ Bonding of tungsten mono‐block with F82H tube
by HIP‐ Detachment experiments in LHD, by• Impurity gas puffing• Edge density limit at high density
Pert rbation)• RMP (Resonant Magnetic Perturbation)
Plasma stored energy

Schematic of the W
divertor plate brazed withcopper alloy tube

Line‐averaged electron density
Radiation loss

Divertor density

Optimizations of the heat treatment and the sizes of theblock and tube are necessary

Various researches are also ongoing‐ Evaluation of the enhanced radiation loss by Ne‐ Spectroscopic study on W
‐ Interaction between W and hydrogen‐ Plasma irradiation test of PFC materials

Divertor temperature

Divertor density and temperature
was reduced by Ne puffing‐ Neutral particle simulation (EIRENE)‐ MD simulation on C and W‐ Configuration optimization for asymmetry mitigation‐ Strike‐point sweeping for erosion mitigation
49 / 79

Summary of [2] Research Achievements andEnvironment [2] 研究成果

Fusion Engineering
Research Project
in NIFS

Points of Evaluation

2

Whether or not FERP is achieving
internationally evaluated results
throughout the study on helical fusion
reactor
ヘリカル型核融合炉の研究を進めることにより、国際的に⾼いレベルの成果を上げているか

Facts
Many research results have been achieved throughout
the reactor design activity and related R&Ds in FERP:
 150
5 p
presentations in total have been ggiven in theinternational conferences (invited: 14, oral: 26)
 217 papers in total have been published

Conceptual design of the helical reactor FFHR‐d1 is
proceeding:
2‐1

Helical fusion reactor design
ヘリカル型核融合炉の設計

R&D toward establishment of the
2‐2 engineering basis
⼯学基盤構築に向けた研究 Considerations on plasma, SC magnet, blanket, divertor,
in‐vessel components, structure, neutronics, etc.
 37 presentations related to the FFHR‐d1 design have been
given in the international conferences (invited: 4, oral: 3)
 81 papers related
l d to theh FFHR‐d1
d ddesign hhave bbeen
published

R&Ds on SC magnet, blanket, low‐activationmaterials, divertor, and tritium have been conducted:
 In collaboration with universities
 113 presentations on these R&Ds have been given in theinternational conferences (invited: 10, oral: 23)
 136 papers on these R&Ds have been published
50 / 79

[3] Encouragement of Joint
Activities and Collaborative
Research

Fusion Engineering
Research Project
in NIFS

共同利⽤ 共同研究の推進
共同利⽤・共同研究の推進(3‐1) Whether or not NIFS is promoting collaboration as COE,
concentrating the high research ability of universities
and others
⼤学等が有する⾼い研究能⼒を結集して、COEとして共同研究を適切に進めているか(3‐2) Whether or not NIFS is contributing to the development
off researchh att universitiesi
iti
⼤学の研究発展に寄与しているか(3‐3) Whether or not FERP is collaborating with andcontributing to international activities of ITER, BA, andothers?
ITER計画やBAなど国際的な活動との連携、貢献を図っているか

Fusion Engineering
Research Project
in NIFS

51 / 79(3‐1) Collaboration
Whether or not NIFS is promoting collaboration as COE, concentrating the highresearch ability of universities and others
⼤学等が有する⾼い研究能⼒を結集して、COEとして共同研究を適切に進めているか

Collaborations on Fusion Engineering in 2010‐2013: 542 in Total
 66 under
266
d NIFS collaborations
ll b ti‐ 52 on reactor design‐ 69 on SC magnet system‐ 101 on in‐vessel components‐ 25 on isotope / environment‐ 19 on numerical simulation / analysis

64 under LHD project collaborations
91 under bilateral collaborations
40 with private companies
81 by external funds (71 by grant‐in‐aid of MEXT)
52 / 79

Fusion Engineering
Research Project
in NIFS

Statistics ofCollaboration

General joint research collaborations

LHD project research collaborations

Bilateral research collaborations

Research collaborations with private companies

Fusion Engineering
Research Project
in NIFS

53 / 79(3‐2) Research at Universities
Whether or not NIFS is contributing to the development of research at universities
⼤学の研究発展に寄与しているかTokai University‐ Plasma operation scenario‐ HTS (YBCO) current lead

The
The University of Tokyo‐ System code
‐ Application of HTS in Mini‐RT‐ Material study for liquid blankets

Tohoku University‐ HTS (YBCO) mechanical joint‐ MHD pressure loss mitigation‐ Fatigue life evaluation‐ Heat removal in FLiBe blanket‐ W alloy

Kyushu University‐ Tritium balance‐ Hydrogen isotope separation‐ Neutron irradiation effect on SC magnet‐ Environmental dynamics of OBT

Kagoshima University‐ Stability of HTS (MgB2) conductor

Sophia University‐ Current inhomogeneity in CIC conductor

Toyohashi University of Technology‐ Detection of partial discharge in SC magnet

Hokkaido University‐ Plasma irradiation effect on H/He retention

Nagano National College of Technology‐ Hydrogen isotope oxidation

Kyoto University‐ W coating on low activation materials‐ Energy conversion in divertor

Akita University‐ Hydrogen isotope trappingShizuoka University‐ Dynamics of hydrogen transport

Osaka University‐ PWI study using laser / ion beam induced plumeKanazawa University‐ Graphite divertor tile

The University of Electro‐Communications‐ Spectroscopic study of W by EBIT

Niigata University‐ Charge exchange between W and H

Nagoya University‐ Neutron measurement system‐ 6Li isotope separation

University of Occupational and Environmental Health‐ Biological effect of T

Akita University‐ Hydrogen isotope trapping… and so on

54 / 79

Example of Cooperative Activities in the NIFS
Fusion Engineering Research Project

Fusion Engineering
Research Project
in NIFS

e.g., Recovery efficiency ofhydrogen isotope‐ Important to elucidate the tritiumtransport in fusion reactor

Lab. scale experiment ofhydrogen circulation in
Shizuoka Univ.
‐ NamedN
d “EXPRESS”‐ Consists of plasma formation system,gas purification system, and gas stock
Schematic of “EXPRESS” in Shizuoka Univ.

55 / 79

Fusion Engineering
Research Project
in NIFS

Collaboration Network
Carried out in coordination with the research promoted by Universities
High heat test andof hydrogen
Divertor analysis
in surface
Coordination research

KyushuTohokuKagoshima

Tokai(2) Large‐scale high‐field SC magnet
research

TI Tech

Tokyo

Osaka

Seikei

Kyoto

Coordination research

SC magnet
test facilitiesSC
magnet
g

(3)

(2)

(4)

SC magnet
innovative
research

Blanket

NIFS

Tokyo

TI TechKyushu(4) Long life liquidblanket research

TohokuToyama

Osaka

Kyoto

Hydrogen test andmeasurement
equipment

equipment
Coordination research

Researches of liquid metal
and molten salt for liquidblanketThe University of Tokyo

Tokai

Shimane

Kyoto

Shizuoka

Tsukuba

Tritiums prototyping,
Material Material
testing and analysis

Osaka

HiroshimaTohoku(1) Low‐activation
structural materials
research

Ehime

Muroran

Hokkaido

Hachinohe

Kyoto

Osaka

(1)

Coordination research

Fukui

Hokkaido(3) High heat flux
plasma‐facing
plasmafacing wall
research(5)

Heat and mass flow loop
equipment

Tohoku University

TohokuKyushuKyushu, Kyoto University

KyushuResearch oftungsten coatingon the low
activationmaterials

Coordination research

Akita

Hokkaido((5)) TraceT
tritiumii
Ibarakicontrol technology
research
NagoyaO&E HealthResearch of low activationmaterial strength mixing thenano‐sized particle under the high University of Toyama
Tohoku University temperatures

ToyamaShizuoka
KyushuResearch of tritium
decontamination in theplasma and tritium
behavior in the material

56 / 79

Fusion Engineering
Research Project
in NIFS(3‐3) International Activities
Whether or not FERP is collaborating with and contributing to international
activities of ITER, BA, and others?
ITER計画やBAなど国際的な活動との連携、貢献を図っているかITER‐ SC magnet: ITER‐TF coil, cryo system‐ NBI: beam simulation, experiments

BA‐ JT‐60SA: SC magnet‐ IFERC DEMO R&D: RAFM, SiC, PWI exp. in JET‐ IFERC DEMO Design: cost model‐ IFMIF‐EVEDA: fatigue life evaluation

TITAN‐ Permeability test of Er2O3 coated RAFM in Idaho National Laboratory (INL)‐ MHD pressure loss experiment in UCLA (with Tohoku university)‐ Irradiation effect on jointing materials (with Osaka university)

GENIE‐ Provision of atomic and molecular database

Fusion Engineering
Research Project
in NIFS

57 / 79

Collaboration with ITER
SC magnet and cryo system‐ ITER‐TF coil testing‐ Cryo system simulation code C‐PRESTNeutral Beam Injection (NBI)‐ Beam simulation‐ Experiments in NIFS test stand

Performance test of the
ITER‐TF connection part in
NIFS

Simulation results of the heattransfer to LHe reservoir, by C‐
PREST made in NIFS

3D‐beamlet simulation including secondary
charged particles
58 / 79

Fusion Engineering
Research Project
in NIFS

Collaboration with BA
JT‐60SA‐ SC magnet testingIFERC‐ Precipitation behavior of F82H‐BA07 during aging and creep‐ Electrical
El t i l conductivity
d ti it anddhhydrogendpermeability
bilit off SiC materials
t i lunder irradiation‐ Cost model‐ PWI experiment in JET
Performance test of the JT‐60SA
CS model coil in NIFS

IFMIF‐EVEDAFirst wall

‐ Fatigue life evaluation
using small specimen

60Co

Gamma-ray(Takasaki)
X-ray
FissionReactor(JMTR)

60Co
Gamma-ray(Osaka Univ.)

DT Neutron(FNS)

The extraction residue of RAFM (Reduced Activation Ferrite Materials) andthe particle size distribution (in each bar)

Fusion Engineering
Research Project
in NIFS

60Co

Gamma-ray(Osaka Univ.)

CVD-SiC (Rohm&Haas)
CVD-SiC (MES)
4H-SiC (semi-insulating)
4H-SiC (n-type)
SiC (Hexoloy/NITE/Hexoloy)
Y2O3
CaZrO3
Er2O3

The radiation‐induced conductivity invarious ceramic materials

59 / 79

Collaboration on TITAN
 Japan‐US collaboration on Tritium,
Irradiation and Thermofluid‐ Following JUPITER and JUPITER‐II

R
RecenttT
Topicsi
Permeability of F82H withand w/o Er2O3 coating‐ Permeability test of Er2O3
coated F82H using tritium inIdaho National Laboratory‐ Mitigation of MHD pressure loss
by partial electrical isolation(with Tohoku University)‐ Irradiation effect on jointing
materials
i l ((with
i hO
Osaka
k U
Univ.)i )Pressure loss dependence on theflow velocity of Li‐Pb in a channel
with electrical isolation on three‐sides
60 / 79

Fusion Engineering
Research Project
in NIFS

Collaboration on Atomic andMolecular Database
NIFS is Providing the largest
database to GENIE

JPN
NIFS
JAEA

USA

GENIE

ORNL

CHN

‐ GENIE is the worldwide search engine ofatomic and molecular database‐ Organized by DCN (IAEA)NISTCRAAMDGENIEA General Internet Search Engine for Atomic Data
Transition
Probabilities
Wavelengths
Energy Levels

DCN
KOR
NFRI

Ion: C IV
Ion: C 3 +RUS
Kurchatov
Inst.

Enter wavelength in Å:UK(AM & PMI Data Center Network)

AtomicAi andd MolecularM l l DataD
Unit, IAEA

KAERIElectron Impact
Cross Sections
and/or Rate
Coefficients

From 1

ADAS

GER
FZJ

to 1 0 0 0 0

NIST Atomic Spectra
Database
Kurucz's CD-ROM 23
Atomic Line List
v.2.04
TOPbase (Opacity
Project)
Kelly Atomic Line
Database
MCHF/MCDHF
Collection
KAERI AMODS
Spectral Lines
CAMBD Atomic
SpectraSpectr-W3
Go fo r A/E/lam b d a

Excitation
Cross
sections
Ionization
R
Rate
Dielectronic
recombination coefficients

IAEA ALADDIN
Database
NIFS AMDIS
Database
CAMBD
Collisional
Processes
NIST Atomic
Cross Sections
OPEN-ADAS
Spectr-W3
Go fo r sig m a/R

リ セッ ト

リ セッ トComments | ALADDIN | AMBDAS | A+M Data Unit | IAEA

http://www‐amdis.iaea.org/GENIE/

61 / 79

Summary of [3] Encouragement of Joint Activities andCollaborative Research [3] 共同利⽤・共同研究の推進

Fusion Engineering
Research Project
in NIFS

Points of Evaluation

Facts

Whether or not NIFS is promoting
collaboration as COE, concentrating the 542 collaborations have been performed on theengineering issues of33‐1 high research ability of universities and SC magnet,
t cryo system,t
reducedd d activation
ti ti material,t i lothers⼤学等が有する⾼い研究能⼒を結集して、COEとして共同研
究を適切に進めているか

Whether or not NIFS is contributing to
the development of research at
3‐2
universities

blanket, divertor, tritium, reactor design, and so on

A lot of important researches have been performed atuniversities, under collaboration with NIFS

⼤学の研究発展に寄与しているか

Whether or not FERP is collaboratingwith and contributing to international
3‐3 activities of ITER, BA, and others?

FERP is contributing to ITER, BA, TITAN, atomic andmolecular database, by closely cooperating with them

ITER計画やBAなど国際的な活動との連携、貢献を図っているか62 / 79

[4] Human Resource Development

Fusion Engineering
Research Project
in NIFS~ Whether or not FERP is bringing up young researchers who can
support long‐range growth of international fusion study
⼈材育成 〜核融合研究の⻑期的な発展を⽀える国際的に活躍できる⼈材の育成に貢献しているか 22 papers have been written by the students grown up through thecollaboration with FERP A half of the students are now working in fusion‐related technology
fields‐ Graduated from universities collaborating with FERP
‐ ~420 collaborations have been carried out by FERP anduniversities in these 4 years

Breakdown of published papers

Fusion Engineering
Research Project
in NIFS

63 / 79

TG Leaders of FERP are YOUNG

Most of them are the thirties or forties‐ Each of them is aware of his/her responsibility for realizing thefusion energy

Young Researchers
are nominated as the
TG leaders!

64 / 79

Fusion Engineering
Research Project
in NIFS[5] Future Plan
~ Whether or not the future plan is appropriately pointing at themedium‐ to long‐term target

将来計画 〜⽬標に向けた今後の研究計画は適切か。特に、中⻑期的展望を⾒据えたものとなっているかNext Move on Reactor Design‐ New approach‐ 3rd round‐ Starting peer review with JAEANext Move on R&D‐ Promotion of the 5 major R&Ds toward real‐scale and real‐environment test in the 3rd mid term

65 / 79

Fusion Engineering
Research Project
in NIFS

New Approach

Starting discussion on FFHR-d1A, d1B, d1C,
and c1
 FFHR‐d1A is the base for 3D designs with a modified
Aspect ratio by reducing the Shafranov shift
 FFHR‐d1B is a flexible design for the ignition core withthe magnetic (B) field enhanced by 20%
 FFHR‐d1C is another flexible design with Configuration
optimization of vertical field coils
 FFHR‐c1 is a sub‐ignition version as “before‐demo,
compact and component‐test”

8
W

7
B ~R

6

c
c
(similar confinement)~ 160 GJ

FFHR-d1B

5
FFHR-c1.2

4

mag

FFHR-c1.1-3/4

FFHR-d1A

37 A/mm 2
30 A/mm

3
LHD

2

2

FFHR-c1.0

jc ~ 25 A/mm 2

W

mag

~R

3
c

B

2
c

~ 70 GJ

1
0
0

5

10

15

20

R (m)
c

66 / 79

Fusion Engineering
Research Project
in NIFS

3rd Round
Just started since FY2013

67 / 79

Fusion Engineering
Research Project
in NIFS

Starting Peer Review with JAEA
Renewal of the collaboration style with JAEA

1994: Collaboration on FFHR design started
2013: All Japan combined team for DEMO development
planning launched

ITER
BA

JAEA

Reinforcement of collaboration with
JAEA
NIFS (FERP)

MEXT

Universities(to be included)

Fusion Research
Development
Working GroupAll Japanp
Combined Team

[Schedule]
25‐27 Nov. 2013: 1st Meeting @ Rokkasho
Feb./Mar. 2014: 2nd@Toki
May/Jun. 2014: 3rd@Rokkasho
2014: 4th@Toki

Problem‐solving by peer
review‐ Helical reactor design by NIFS (FERP)‐ Tokamak reactor design by JAEA

68 / 79

Fusion Engineering
Research Project
in NIFS

Next Move on R&D
Toward real-scale and real-environment test in the 3rd mid term

(2) Large‐scale, high‐field
superconducting magnet(3) High heat flux plasma facing
components

Establishment of engineering baserequested by
Fusion Research Working Group Proposal of stable and long‐life
superconducting magnet

 Proposal of stable and long‐lifeplasma‐facing wall
Di t plasma
Divertorl

SC magnet
Mag.
field
Current

Establishment of
Future fusion reactor
conductor testing
method Stable, safe and secure basic energy source World standard of Japanese origin
 Human resource development０ Environmental preservation(4) Long‐life liquid
breeder blanket

Divertor plate(5) trace tritium
handling technology

1GW electricity productionSC
magnetEvaluation of theeffect of strong
magnetic fieldResearch of tritium
accounting technology

accelerate Proposal of safe and long
long‐life
life power
generation system

Research of codes andstandards(1) Reduced activation materials

Fast neutron
Improvement ofhigh‐temperature strength

Reactor coreplasmaEstablishment ofcontrol methodof hydrogen
retention

 Development of safe and long‐life materials

 establishment of highly‐
accurate, highly‐efficientand safe trace tritium
processing systemevacuation

gas with T

detection

separation
vacuumvesseloxidation
gas introduction

T collection
vessel69 / 79

Summary of [4] Human Resource Development and [5]Future Plan [4] ⼈材育成 [5] 将来計画

Fusion Engineering
Research Project
in NIFS

Points of Evaluation

4

Whether or not FERP is bringing up
young researchers who can support
long‐range growth of international
fusion study
核融合研究の⻑期的な発展を⽀える国際的に活躍できる⼈材の育成に貢献しているか

5

Whether or not the future plan isappropriately pointing at the medium‐to long‐term target
⽬標に向けた今後の研究計画は適切か。特に、中⻑期的展望を⾒据えたものとなっているか

Facts
FERP is bringing up young researchers: 22 papers have been written by students who
collaborated with FERP A half of the students found their jobs in the fusion
fusion‐related technology fields
 Most of the TG leaders of FERP are 30ies or 40ies who are
actively playing important roles in the international fusion
community

The future plan of FERP is appropriate: Reactor design will proceed to the next step, to draw aconcrete view of the helical fusion reactor
 R&Ds and collaborations with universities will be
accelerated by operating the devices provided by thellarge
supplementarylt
b d t inbudgeti FYFY201270 / 79

Fusion Engineering
Research Project
in NIFS

Points of Evaluation based on Proposals fromthe External Evaluation in FY2009

1. Whether or not fusion engineering research is developed across theboard with the emphasis on helical reactors design
ヘリカル炉設計を軸に組織横断的に核融合⼯学研究を発展させているか

2. Whether or not NIFS is acting as the center for national research on
advanced blankets and reduced activation materials as well as taking theleadership from the international research point of view
核融合科学研究所が先進ブランケット及び低放射化材料研究の国内拠点となり、国際的にも研究の主導的⽴場を確保しているか

3. Whether or not NIFS continues to develop superconducting coils for fusion
reactor development
核融合炉開発に向けた超伝導コイル研究を推進しているか

4. Whether or not efforts are being made to encourage young

researchers to participate in the fusion rector research project
核融合炉研究プロジェクトを担う若⼿研究者を育成しているか

5. Whether or not the fusion engineering research project conducted by NIFS
contributes to the establishment of academic fundamentals for helicalfusion reactors
核融合科学研究所の進める核融合⼯学研究の発展がヘリカル核融合炉実現のための学術体系の構築に⼤きく貢献しているか

Fusion Engineering
Research Project
in NIFS

71 / 79

Tasks have been Taken OverResearches before 2010 are continued with additional tasks in FERP since 2010
Task

Subject
LHD

R&D for Reactor

Material
Corrosion
Coating
H‐monitor
Neutronics
Maintenance
Reactor size
Ignition access
Neutronics
SC magnet
Tritium
Monitor

Tritium Recovery

Prepare for
Deuterium
Experiments in LHD[SC Magnet](1) Higher field by subcooling(2) Dynamic control of plasma axis(3) High reliability of LHD SC system(4) Nb3Sn, Nb3Al conductor/coil(5) HTS, MgB2 development(6) Thermoacoustic applications(7) Cryotarget(8) SC power line
(9) Neutron irradiation effect(10) New SC wires(11) Conduction cooled magnet

 Conductor development
 Coil winding Cooling

Radiation effects on V‐alloy weld joints
W coating on V‐alloys
Thermal creep of RAFM and V‐alloys
Corrosion of RAFM in Flibe and Flinak
Corrosion of RAFM and V‐alloys in Li
Fabrication of insulator and T‐barrier coating
H‐monitoring system in liquid breeder
Tritium Breeding Ratio for FFHR
Experimental check[In‐Vessel Components]

Long‐life blanket
Wide ports
Blanket space
Magnetic energy
Heating power
New regime for SDC
Neutron economy
Large helical coils
Cooling
Support post

 Power supply
 Generator

Hydrogen Pump
Separation of Hydrogen and TritiumHigh sensitive T gas monitor
H/T separation with CECE
Low loss oxidation material
Compact & high efficient dehumidifier
Compact T recovering system
Develop H/T separation with ZrNi
T retention, desorption and removing
Measuring T in concreteHigh sensitive H analyzer
Design of RI monitoring cart
Biological effectEnvironmental effect of tritium[Cryogenic]
 Cryogenic system
 Coil power supply system[Blanket] Blanket systemydevelopmentp Blanket design

 In‐vessel component development

 Structural design
 Maintenance[Design Integration][Building Layout][Power Supply][Tritium][Operation Control]

Subject
Large‐scale high‐field conductor testing facility
CIC conductor & winding
Indirect ‐cooling LTS conductor & winding
HTS conductor & winding
EM force support structure
Cryogenic system
Bus‐line and current‐lead
Coil power supply system
Radiation shieldg blanket
Breeding
Heat, hydrogen isotopes recovery system
First wall
Vacuum vessel
Divertor
Remote maintenance
Task setting and project management
Conceptual design of helical fusion reactor
Layout design and construction process
Reactor building design
Generator and power supply system
Transmission and hydrogen production
Tritium fuel balance
Tritium safety handling
Tritium decontaminationg
Tritium monitoring
Safety analysis and control system
Burn control[Core Plasma]

Plasma experiment
MHD equilibrium and stability
Neoclassical transport
Alpha heating
Anomalous transport
Plasma operation scenario[Plasma Heating]

NBI
ECH
ICRF
PelletInvestigation of available diagnostics
Neutron diagnostics
Spectroscopic diagnostics
Interferometer / reflectmeter
Thomson scattering[Fueling][Diagnostics]

72 / 79

Fusion Engineering
Research Project
in NIFS

Points of Evaluation based on Proposals fromthe External Evaluation in FY2009
FY2009FY2013
FERP is developing the fusion engineering research:

Whether or not fusion engineering research is With the researchers from various scientific fields
1 developed across the board with the emphasis on
 Collaboration with LHD project / Num. Sim. Res. Project onhelical reactors design
FFHR d is
FFHR‐d1
i successfully
f ll ongoingi

Whether or not NIFS is acting as the center for
FERP is internationally leading the study on advanced
national research on advanced blankets andblanket and reduced activation materials:
2 reduced activation materials as well as taking the  Especially on the FLiBe blanket and V alloyleadership from the international research point  Twin loops for molten salt / LiPb circulation test with 3 T
magnetic field will be the “only one” in the worldof view
Whether or not NIFS continues to develop
3 superconducting coils for fusion reactor
development
Whether or not efforts are being made to
4 encourage young researchers to participate in
the fusion rector research project
5

FERP is continuing to develop three types of SC magnet
for fusion reactor:
 Collaboration with ITER and BA (JT‐60SA)
 Jointed winding of HTS helical coil is the new original idea

FERP is encouraging young researchers to join:
 Young researchers are nominated as TG leaders Important issues are assigned to young researchers

Whether or not the fusion engineering research
project conducted by NIFS contributes to theestablishment of academic fundamentals forhelical fusion reactors

Fusion Engineering
Research Project
in NIFS

YES, we think so!
HOW about you?
73 / 79

Summary of Publications andCollaborations on Fusion Engineering
R&D
136

1. Publications in 2010‐2013: 217 in total
136 on R&D(17 on SC magnet & Cryogenics, 25 on Low activation materials,
62 on Blanket & First wall, 46 on Divertor, 56 on Tritium & Safety)

81 on Reactor Design(28 on Concept & System design, 21 on Core plasma control,
11 on Plant equipment & related technology)

Non‐NIFS
members81

81 written by non‐NIFS staffs
22 written by students

Reactordesign81
Students(22)

NIFS
members136

2. Collaborations in 2010‐2013: 542 in Total
266 under NIFS collaborations(52 on reactor design, 69 on SC magnet system, 101 on in‐vessel components, 25 on isotope /w/ Private
environment, 19 on numerical simulation / analysis)

64 under LHD project collaborations
91 under bilateral collaborations
40 with private companies
81 by external funds (71 by grant‐in‐aid of MEXT)

companies
40

External funds
81
Bilateral
NIFS
91
collaborations
LHD project266
64
74 / 79

Fusion Engineering
Research Project
in NIFS“Interim Report on the Conceptual
Design of the FFHR‐d1 Helical Fusion
Reactor” has Come Out

Reduced version was
p blished in Journal
published
Jo rnal of
Plasma and Fusion
Research

75 / 79

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2013_06/jspf2013_06‐359.pdf

NIFS Fusion Engineering Research Project member
Fusion Engineering
Research Project
in NIFS(1‐2) Whether or not
the organization of
FERP is coincident with
its target and properly
functioning?

1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
32
33
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
51
52
53
54
55
56
57
58
59
60
61
62
63
64

December, 2013

Name

Division or University

Title

TASK ( including design and R&D)

Sakamoto
Morisaki
Sakakibara
OhdachiGoto, M
Narusima
Tanaka, K
Isobe
Yamada, I
Nakanisi
Tokuzawa
Akiyama
Yoshinuma
Shimozuma
Mutoh
Tsumori
Saito
OsakabeYoshimura
Igami
Kasahara
Seki
Mito
Takahata
Imagawa
Sato
Nisimura, K
Uda
Yamada, S
Yanagi
Chikaraishi
Takayama
KawanoIwamotoTanaka, M
Hamaguchi
Obana
NatsumeSagaraMurogaHirooka
Murakami I
Murakami,
Miyazawa
Tanaka, T
Nagasaka
TamuraMasuzaki
Goto, T
Hishinuma
Ashikawa
SakaueKato
Tokitani
Yagi
Watanabe
Yokoyama
SatakeSuzuki
Mitarai
Murakami, S
Kondo
Idei
KozakiBanzaiHigh‐Density Plasma Physics
High‐Density Plasma Physics
High‐Density Plasma Physics
High‐Density Plasma Physics
High‐Density Plasma Physics
High‐Density Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
High‐Temperature Plasma Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Plasma Heating Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Device Engineering and Advanced Physics
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Systems
Fusion Theory and Simulation
Fusion Theory and Simulation
Fusion Theory and Simulation
Tokai Univ.
Kyoto Univ.
Tokai Univ.
Kyushu Univ.
Osaka Univ.

Aso. PProf.
Aso. P
Aso. P
Aso. P
Asi. P
Aso. P
Aso. P
Aso. P
Aso. P
Aso. P
Asi. P
Asi. P
Prof.
Prof.
Aso. P
Aso. PProf.
Aso. P
Asi. P
Asi. P
Asi. P
Prof.
Prof.
Prof. Div.Dir
Emeritus
Prof.
Emeritus
Aso. P
Aso. P
Aso. P
Aso. P
Aso. P
Aso. P
Aso. P
Asi. P
Asi. P
COE
Prof. Exc.Dir
Prof. Div.Dir
Prof.
Prof
Prof.
Aso. P
Aso. P
Aso. P
Aso. P
Aso. P
Asi. P
Asi. P
Asi. P
Asi. P
Asi. P
Asi. P
Asi. P
COE
Aso. P
Aso. P
Asi. PProf.
Aso. P
Lecturer
Aso. P
Visiting P

Fueling
In‐vessel component
Diagnostics
In‐vessel component
Diagnostics
In‐vessel component
Diagnostics
Diagnostics
Diagnostics
Operation control
Diagnostics
Diagnostics
Diagnostics
Plasma heating
Plasma heating
Plasma heating
Plasma heating
Plasma heating
Plasma heating
Plasma heating
Plasma heatingCore plasma
Coil
Coil
Coil
Tritium
Operation control
Cryogenics
CoilPower supply / Cryogenics
Tritium fuel system
Cryogenics
Tritium
Cryogenics
Coil
Coil / Cryogenics
Design Integration and R&D cordination
BlanketBlanket
In vessel components
In‐vesselCore plasma / Design Integration / Fueling
BlanketBlanketIn‐vessel components / Coil / Buliding layout
In‐vessel components / Diagnostics
Buliding layout/Design Integration /Core plasma
Coil / Cryogenics / Power supply
Blanket / In‐vessel components
In‐vessel components
Blanket / In‐vessel components
In‐vessel components
BlanketBlanketCore plasmaCore plasmaCore plasma
Operation control / Core plasmaCore plasma
BlanketPlasma heatingGroup Leader/ Task L / Sub TL
TL
STL
STL
STL
TL
STL
STL

STL

TL

STL
STL

STL
GL of SC magnet
STL
STL
TL
TL
STL
TL
TL
STL
STL
GL of Design Imtegration
GL of In‐vessel
STL
TL
TL
STL
TL
STL
TL
STL

STL
STL

TL
STL

Secretary

76 / 79

Fusion Engineering
Research Project
in NIFS(1‐3) Whether or not an appropriate research environment isprovided for the establishment of academic fundamentals

Budget for Fusion Engineering Research Project
250

Million JPY• NIFS facility budget is 4.8 Billion JPY
in FY2013.

200
150

• Annual budget for NIFS collaboration
related to fusion engineering is about
100 Million JPY, which is mainly usedin universities.

Outside Funds
Special Budget

100

Annual Budget

50
0FY2010FY2011FY2012FY2013

Supplementary budget of 2.4 Billion JPY for facility
Requested for FERPFY2010Special Budget(Facility + Operation)

0.93

FY2011FY20120.87

FY20130.77

0.63

FY2014FY2015

0.50

0.32

Total

4.00

BillionJPY

77 / 79

Fusion Engineering
Research Project
in NIFS

Establishment of fusion engineering areaby 5 large
large--scale experimental researches(2) Large-scale, high-field
superconducting magnet

Establishment of engineering baserequested by
Fusion Research Working Group¥ 1.20 B JPY
 Proposal of stable and long‐life
superconducting magnet

Establishment of
Future fusion reactor
conductor
testing method
 Stable, safe and secure basic energy source World standard of Japanese origin
 Human resource development０ Environmental preservation(4) Long‐life liquid
breeder blanket¥ 0.810 81 B JPY(3) High heat flux plasma facing
components¥ 0.91 B JPY
 Proposal of stable and long‐lifeplasmaplasma‐facing
facing wall
Establishmentof control
method ofhydrogenretention(5) trace tritium
handling technology¥ 0.20 B JPY

1GW electricity production
 establishment of highly‐
Research of tritium
accurate, highly
highly‐efficientefficient andaccounting technology
safe trace tritium processing
systemResearch of codes andstandards

accelerate Proposal of safe and long‐life power
generation system

Evaluation of theeffect of strong
magnetic field

FERP requested
the total 4 Billion JPY
in 6 years for facility andoperation(1) Reduced activation materials¥ 0.88 B
Improvement ofhigh‐temperature strength Development of safe and long‐life materials

78 / 79

Fusion Engineering
Research Project
in NIFS

Year
2010
2010
2010
2011
2011
2012

2012
2012
2013

[2] Research Achievements~ Whether or not FERP is achieving internationally evaluated results
throughout the study on helical fusion reactor

International Conference
26th Symposium on Fusion Technology(SOFT 2010)
9th International Conference on Tritium
Science and Technology (TRITIUM2010)
19th ANS Topical Meeting on theTechnology of Fusion Energy (TOFE2010)
10th International Symposium on Fusion
Nuclear Technology (ISFNT‐10)
15th International Conference on Fusion
Reactor Materals (ICFRM‐15)
20th International Conference on Plasma
Surface Interactions in Fusion Devices(PSI‐20)20th ANS Topical Meeting on theTechnology of Fusion Energy(TOFE2012)
27th Symposium on Fusion Technology(SOFT2012)
11th International Symposium on Fusion
Nuclear Technology (ISFNT‐11)

Presentations
by FERP and
Totalcollaborations

Ratio

Reference

12

547

2.2%

FED Vol.86 Issues 6‐8, 9‐11

17

170

10.0%

FST Vol.60 No.3,4

13

145

9.0%

FST Vol.60 No.1,2

12

215

5.6%

FED Vol.87 Issues 5‐6, 7‐8

22

222

9.9%

JNM Vol.442 Supplement 1 / FST
Vol.61 No.1

22

238

9.2%

JNM Vol.438 Supplement

9

161

5.6%

FST Vol.64 No.2,3 (3/94) + Book of
Abstract

11

510

2.2%

FED Vol.88 Issues 6‐8, 9‐10

16

525

3.0%

ISFNT‐11 Book of Abstract

79 / 79

Results of FERP Evaluation 2013
Number of persons[2](2)Research[2](1)Helical
Aimed at[1](2)Research [1](3)Research[3](1)Role as
Fusion Reactor Constructing
SystemInfrastructure
COE
Designan Engineering
Foundation[3](3)Linkages
with ITER[3](2)Commitm
Project, BA
ent toActivities, andUniversities
International
Activities

[4]
Human
Resources
Development[5]
Future Plans

Items[1](1)Settingof Objectives

S

7

6

7

10

4

8

5

3

4

1

A

9

10

9

5

10

9

11

10

6

13

B

1

1

1

2

3

0

0

4

7

3

C

0

0

0

0

0

0

0

0

0

0

Averagescores

4.35

4.29

4.35

4.50

4.06

4.47

4.31

3.94

3.82

3.88

S

Extremely highly commendable

5

A

Highly commendable

4

B

Commendable

3

C

Adequate

2

D

Inadequate

1

Evaluation Scoring※ This table contains all the scores given
by both Japanese and foreign reviewers.
Total numbers vary by item because somewere left blank.

Evaluation Items

Items
[1]

（Establishment of research system and environment)[1](1)

Whether or not the target of FERP, initiated in JFY2010, is appropriate[1](2)

Whether or not the organization of FERP is coincident with its target and properly functioning[1](3)［2］

Whether or not an appropriate research environment is provided for the establishment of academic
fundamentals(Research achievements)
Whether or not FERP is achieving internationally praised results through the study of the helical fusion
reactor[2](1)

Helical fusion reactor design[2](2)

R&D toward establishment of the engineering basis［3］(Encouragement of joint activities and collaborative research）[3](1)

Whether or not NIFS is promoting collaboration as a COE, focusing the high-level research abilities ofuniversities and research institutes[3](2)

Whether or not NIFS is contributing to the development of research at universities[3](3)

Whether or not FERP is collaborating with and contributing to international activities of ITER, BA, and others[4]（Human resources development）
Whether or not FERP is nurturing young researchers who will support the long-term growth of international
fusion research[5](Future plans）
Whether or not the future plan is pointing appropriately toward the medium- to long-term targets

Item-by-item average scores
5.00
4.75
4.50
4.25
4.00
3.75
3.50
3.25
3.00
2.75
2.50
2.25
2.00
1.75
1.50
1.25
1.00
[2](1)Helical
Fusion[1](1)Setting [1](2)Research [1](3)Research
Reactorof Objectives
SystemInfrastructure
DesignAverage scores

4.35

4.29

4.35

[2](2)Research
Aimed at
Constructing [3](1)Role asan
COE
Engineering
Foundation

4.50

4.06

[3](3)Linkages
with ITER[4][3](2)Commit
Project, BA
Humanment toActivities, and Resources
Universities
International Development
Activities

4.47

4.31

3.94

4.50

3.88

4.35

[1](2)Research System

4.00

4.29

3.50
3.00

[4]
Human Resources Development

2.50

3.82

[1](3)Research Infrastructure

2.00

4.35

1.50
1.00

[3](3)Linkages with ITER Project,
BA Activities, and International
Activities

3.94
4.50

4.31
[3](2)Commitment toUniversities

4.06
4.47
[3](1)Role as COE

3.88

Average score per item

[1](1)Setting of Objectives
5.00[5]Future Plans

3.82

[5]
Future Plans[2](1)Helical Fusion Reactor
Design[2](2)Research Aimed at
Constructing an Engineering
Foundation

Inter-University Research Institute Corporation
National Institutes of Natural Sciences

National Institute for Fusion Science322-6 Oroshi-cho, Toki, Gifu, 509-5292, Japan

http://www.nifs.ac.jp/