National Institute of Natural Sciences
National Institute for Fusion Science

NIFS Peer Review Reports in FY2018

March, 2019

National Institute for Fusion Science
Advisory Committee External Peer Review Committee

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Contents
Chapter 1 Background ······························································································· 1

Chapter 2 Summary of the Evaluation, and Recommendation ················· 5[1] Summary of Evaluation ··················································································· 5[2] Recommendations ························································································· 10

Chapter 3 In Closing ································································································· 12

Documents
1. 2018 External Peer Review Presentation Materials

References
1. Table of Evaluation Results for the 2018 External Peer Review-2-Chapter 1 Background
The National Institute for Fusion Science (below as NIFS) was established in 1989 as aninter-university research institute, and utilizes the Large Helical Device (below as LHD) as theprincipal device to advance fusion research in universities in Japan.
The LHD, which was planned by bearing the support and the expectations of the fusion
community, has the special characteristic of producing the heliotron-type magnetic field, which is anidea unique to Japan. In addition to generating high-performance helical-type plasma through highpower heating, NIFS is advancing with experimental research that aims to clarify physical andtechnological issues for realizing the toroidal magnetic field confinement fusion reactor. On the other
hand, parallel with this, in analyses of fusion plasmas having fundamental complexities, theoreticalresearch that uses large-scale simulations is essential. For that reason, a supercomputer for exclusive
use was introduced at NIFS. We are advancing with leading-edge research by making thissupercomputer at NIFS available for use to fusion theory researchers in Japan through collaborative
research. Moreover, since 2010, in order to further strengthen the centripetal power of NIFS as a Centerof Excellence (below as COE) in the field of plasma and fusion research we have organized threeresearch projects, these being LHD, theory and simulation, and reactor engineering. Looking forward
toward achieving the fusion reactor, initiated research programs will integrate these research results.
In addition to having revised the research structure within NIFS and having placed all
research staff in one research department, by establishing a research system that enables participation
by free will in research projects and has enabled easier cooperation in the three projects of LHD, theory
and simulation, and reactor engineering than in the past, we are increasingly able to respondresourcefully to new topics.
In this period, there have been changes to the structure of the domestic academic researchsystem. Since 2004, NIFS has been a research institute under the Inter-University Research InstituteCorporation National Institutes of Natural Sciences (below as NINS) for enhancing further thedomestic research collaboration. Upon becoming an inter-university research corporation, a system
for mid-term goals and mid-term planning spanning six years was introduced, and a system of annual
evaluations regarding the progress, too, was introduced. This annual evaluation focuses primarily uponadministrative management. However, at NIFS it has been determined that receiving external
evaluations of research results is important. Under the NIFS Advisory Committee, each year anExternal Peer Review Committee is organized and the members evaluate the research. The topics ofevaluation are determined by the Advisory Committee. The evaluation is undertaken by the membersof the External Peer Review Committee, which is composed of experts who are external members of
the Advisory Committee and external experts who are appropriate for evaluating the topics. The
External Evaluation Committee submits its evaluation results to the Advisory Committee. Then, NIFS,-1-

together with making the results public by uploading that information to the NIFS homepage, utilizes
this information to improve research activities in the following years.
The topics for evaluation for the External Peer Review Committee are discussed and decided
upon by the Advisory Committee, and those topics for evaluation differ each year. Most recently, in2015 the Numerical Simulation Reactor Research Project, in 2016 Collaborative Research, and in2017 the Reactor Engineering Research Project were topics evaluated by external reviewers. This year,
2018, the “Large Helical Device Project” was selected and reviewed by the external examiners.
As external members of the External Peer Review Committee there were ten external
members from the Advisory Committee and three members from foreign countries. Further, there were
two experts from outside NIFS and one expert from abroad. Thus was the External Peer Review
Committee composed, and thereby the evaluation was undertaken.
The first meeting of the External Peer Review Committee including the Experts’ Committee
was convened on September 18, 2018. The Committee discussed the process for moving forward withthis fiscal year’s external peer review, and decided upon the perspective of the evaluation. On
December 1, 2018, the second meeting of the External Peer Review Committee and Experts’Committee was held. From NIFS was provided a detailed explanation that utilized documents fromthe material of viewgraphs and reports based on the perspectives (see the documents section). A
question-and-answer session also was held. Subsequently, the third meeting of the External Peer
Review Committee and the Experts’ Committee was held on January 25, 2109. Together with holding
another question and answer session with NIFS, evaluation work based on the topics of the evaluationand the coordination of the evaluation work were undertaken. We compiled the external peer review
report (draft) based upon the discussions to this point, and further discussions were held by electronic
mail. Upon confirmation and examination by the External Peer Review Committee and the Experts’Committee, we compiled the final report. Please see Reference Material 4 for the meeting schedule of
the External Peer Review Committee and the Experts’ Committee.
Moreover, in the external evaluation regarding “LHD Project” which was implemented thisfiscal year, the perspectives for the evaluation were determined as follows. The perspectives for theevaluation are considered indispensable in the evaluation of the “LHD Project” promoted by NIFS
which NINS decided upon in the mid-term planning. These perspectives are the basis of the evaluationof achievements and the evaluation of the level of research.
Further, we have consulted the following points in the evaluation which are based upon therecommendations implemented in the External Peer Review Report of the “LHD Project” in 2011 andthe “Deuterium Experiment Implementation Planning” in 2014.

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Recommendations in the External Evaluation Review in Fiscal Year Heisei 23:(1) It is desired that the LHD as the leading device of inter-university research activities continues
to serve as a large scale experimental platform for fusion research in the world.
(2) It is hoped that the installation of closed divertor will be completed and the deuterium
experiment will start as soon as possible in order to push the maximization of the LHD
capability forward.
(3) It is desired that the LHD activity continuously encompass the work for the ITER project andthe BA activities.
(4) It is hoped the LHD project will guide the world’s fusion research and produce internationallycompetitive human resources.
(5) It is desired that a discussion start regarding a plan that looks to the future after the deuterium
campaign is completed.

Recommendations in the External Evaluation Review in Fiscal Year Heisei 26:(1) Referencing improvement of confinement and the preparation of both heating devices anddiagnostic equipment, which are accompanied by the deuterium experiment, we anticipate thatthe contribution to a comprehensive understanding of toroidal plasma will be undertaken
through deepening further discussion of concrete experiment planning formulation together
with enhancing modeling. We anticipate further continuation and support of research networks
throughout Japan that focus on neutron diagnostics, tritium recovery, and plasma-wallinteraction constructed through joint research aimed at the deuterium experiment.
(2) To begin the deuterium experiment on schedule, we anticipate completion without delay of theformulation of the planning for implementation of preparation, the preparation of equipment,
the improvement of facilities, and the establishment of the safety management system, all ofwhich are aimed at the deuterium experiment, under the Division of Deuterium Experiments
Management.
(3) Since NIFS has the standing as an inter-university research institute that summarizes researchin fusion studies at universities, succeeding safely in completing the deuterium experiment isextremely important. In particular, while respecting laws and regulations, respecting theopinions of local residents, and maintaining an awareness of a good balance of academic
development, it is important to respond flexibly. Further, the actual safety management is
expected to proceed politely and steadily in such a way that the appointment period forsupervisors will overlap and that new supervisors will be appointed appropriately.
(4) We can highly evaluate NIFS’ explanations for local residents and cooperation activities withlocal governing bodies over these many years. From now, through achieving safety
management and constant effort, it is hoped that this endeavor will gain understanding and-3-

support for fusion.

The perspectives for the evaluation[Implementation system and the state of implementation](1) Is the implementation system built to achieve deuterium experiments with coordinating
domestic and international researchers?

(From the third mid-term plan)(2) Are preparations of safety management equipment and of facilities and their countermeasures
performed appropriately for starting the deuterium experiments? Was the safety management
system built as planned? (From the third mid-term plan)[Results of initial experiments and future research development](3) Does the LHD project obtain high-performance plasma by the deuterium experiments andproduce excellent research achievements with high academic value?

(From the third mid-term plan)(4) Does the LHD project obtain prospects for development of academic research toward acomprehensive understanding of toroidal plasmas? (From the third mid-term plan)(5) Is preparation of necessary devices and facilities for the main device, heating systems,
diagnostics, and others advanced appropriately according to the research plan of the deuterium
experiments?
(6) Will the LHD project consider further research development towards the realization of a fusion
reactor based on the achievements of the LHD project?

[Promotion of collaboration](7) Does the LHD project play the role of a global COE in the research with helical devices byconstructing and using the research network among domestic and international universities andresearch institutes?
(8) Does the LHD project promote cooperation with and contribute to ITER/BA? Further, does the
LHD project contribute to the research and development of the DEMO reactor? (From the third
mid-term plan)[Human Resource Development and Efforts toward Understanding by Society](9) Does the LHD project contribute to the human resource development of researchers who are
active internationally and lead the domestic and international fusion research?
(10) Does the LHD project cooperate with local governments and engage in deepening theunderstanding of the deuterium experiments by local residents? Does the project also
contribute to achieving a broad social understanding of fusion research?

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Chapter 2 Summary of the Evaluation, and Recommendation
We summarize the key points of the evaluation, and report in writing the recommendation
regarding promotion of the LHD Project.

[ 1 ] Summary of the Evaluation[Implementation system and the state of implementation](1) Is the implementation system built to achieve deuterium experiments with coordinating
domestic and international researchers? (From the third mid-term plan)
Four topical groups centering on the LHD experimental meeting were established, and they
operate the systems which have researchers at universities in Japan as chairpersons. A new LHD
International Program Committee is established as well as the operating system based on the existingachievement, and the implementation system with an eye to promotion of international collaborative
research with foreign institutes is established as well. These systems are highly evaluated. Especially,
increasing the number of researchers from abroad since the LHD International Program Committee
was established and the improvement of the presence of LHD research are highly evaluated. Openresearch system is established with transmitting machine time, daily research report, and othercommunications which are written in English through the Internet. This is also evaluated.
On the other hand, establishing a place to discuss consistency between a domestic
collaborative research submission and an experimental submission of LHD International Program
Committee, and a place to gather collaborative research results are believed to be necessary.

(2) Are preparations for safety management equipment and of facilities and theircountermeasures done appropriately for starting the deuterium experiments? Was the safety
management system built as planned? (From the third mid-term plan)
Systems to complement the experimental research safely such as establishing thedeuterium experiment promotion task force, systematically developing or modifying equipment,
and of radiation control and monitoring system were developed. And the deuterium experiment wasstarted and implemented according to the plan. They are highly evaluated. Also, in the radiation
safety management system, neutron flux monitors, neutron activation foil, and vertical neutron
camera were adopted for neutron yield control, and these measurement instruments are operated
appropriately. Tritium yield is controlled tightly. These preparations are also highly evaluated.

-5-Especially, removal rate in tritium removal system exceeded the initial design value of 95% andachieved 99.8%, which is worthy of note. Furthermore, NIFS Safety Monitoring Committee wasestablished based on the agreement and the memorandum with local government bodies, andoperated appropriately. This is highly evaluated.
It is necessary to endeavor to secure workers’ safety with paying attention to tritium
remaining in the vacuum vessel or exhaust system, and appropriate management of radiation
protection for workers in vacuum vessel.
On the other hand, there is concern for excessive burden on the NIFS staff regarding safetymeasures. In order to implement the continuing safety management, it is necessary to conduct a reviewof necessary matters on a constant basis and devise rational management systems with progress intechnology and sophistication of knowledge.

[Results of initial experiments and future research development](3) Does the LHD project obtain high-performance plasma by the deuterium experiments andproduce excellent research achievements with high academic value?

(From the third mid-term plan)
Early in the deuterium experiments, the initial goal to reach the ion temperature of 10keV
was achieved, and the electron temperature of 10keV was obtained with low electron cyclotron heating
power. And they are highly evaluated. Knowledge regarding academic understanding of isotope effectis absolutely gained, and the understanding is advanced by applying computational science and theory.
Reduction of turbulent transport in the deuterium plasma had been predicted by theoretical researchwith gyro-kinetic simulation before the deuterium experiment started, which is exceeding high results
academically, and is also highly evaluated internationally.

Furthermore, the confinement of high-energy particles in the LHD in the Triton burnup experiment is evaluated, and exhibits the confinement
property equivalent to equally sized Tokamak devices. And they are evaluated.
On the other hand, many unsolved points and points to be conducted including isotope effectstill remain. Thus it is expected to pursue researches continuously and achieve great results. Also, inorder to promote research which requires a large budget, it is vitally necessary to be recognized byresearchers from other research fields, and it is also necessary to publish the research results in highly
evaluated academic journals beyond research fields, and confirm the value.

(4) Does the LHD project obtain prospects for development of academic research toward acomprehensive understanding of toroidal plasmas? (From the third mid-term plan)-6-

The direction of research to clarify the differences of characteristics between Deuterium
plasma and Hydrogen plasma through sophisticated experimental researches such as advancement of
measurement system including D/H ratio measurement method, and behavior of high-energy ionsgenerated by deuterium fusion reaction, is appropriate and highly evaluated. Regarding isotope effecton confinement characteristics, interaction between energetic particles and MHD modes, and others,
it is expected that there will be prospects for academic development of comprehensive understandingof toroidal plasma in complementary studies with LHD experiment and theory/simulation. Regarding
tritium inventory, it is highly evaluated to make it possible to acquire and verify data.
Regarding isotope effect, we cannot say that there are enough experiment results to confirm
the effect, and it is desirable to clarify the complete picture of the isotope effect. We will expect further
progress in academic understanding of isotope effect by devising experiment plans with the knowledge
gained from computer simulation. However, there would be some limitation to flexibility ofexperiment because it is necessity to cope with neutron production and tritium production. Further, it
would be necessity to discuss the possible range of effectively deepening and extending the researchunder the limitation of neutron yield. It is required to clarify overall prospects such as engineeringtasks and comparisons with theory/simulation further.

(5) Is preparation of necessary devices and facilities for the main device, heating systems,
diagnostics, and others advanced appropriately according to the research plan of thedeuterium experiments?
It is highly evaluated that equipment in the vacuum vessel, gas puffing and solid hydrogenpellet injector, closed divertor pumping, cooling water supply system, plasma heating device,
diagnostics device, and relevant analysis code are appropriately prepared for the preparation of devices
and facilities for the deuterium experiments. Also, enhancement of detailed measurement of H/D ratio
and measurement of edge/divertor region will significantly support clarifying the isotope effect in the
future. Thus, we expect the future progress of data-analysis. The monitoring system for tritium
concentration in gas from all pumping systems are meaningful to evaluate tritium balance in addition
to safety warranty. Further research progress will be expected.
There are possibilities that various control parts malfunction under the neutron production
environment, and it is preferable to continue conducting the operation with fail-safe. The negative ion
NBI which was optimized for hydrogen is applied to the operation of deuterium, and it caused theoperation with performance degradation. Therefore, enhancement and adjustment of the system are
required. Since some tritium produced remains in the vacuum vessel, it is necessary to consolidate thesystems to measure tritium distribution on protection plate or carbon tiles, and to examine amechanism of tritium capture.

-7-(6) Will the LHD project consider further research development towards the realization of afusion reactor based on the achievements of the LHD project?
It is evaluated to promote academic research regarding plasma confinement characteristics,
plasma instabilities, and behavior of energetic particles with utilizing high-performance plasma whichwere produced in the deuterium experiments, and develop the physical database required for design
and fabrication for the future helical fusion reactor. It is also evaluated to focus on plasma facing
material research such as divertor under high heat load environment and the research about behaviorof hydrogen isotope in plasma facing material, to accelerate understanding of hydrogen isotope
balance in future fusion reactor and to accumulate necessary engineering database for realization offusion reactor.
For the next step, it is desirable to aim for steady-state sustainment of high performance
discharge for the realization of helical type fusion reactor with incorporating future deuterium
experiment results. Also, under the high results in LHD, FFHR-d1 and others are examined as demo
reactor. It is preferable to be committed to the promotion of more concrete reactor design and researchpromotion of relevant development matters, including future expected deuterium experiment results.
It is desirable to define the academic and the engineering role the LHD experiment will play for therealization of fusion reactor regardless of reactor type, and pursue research with taking a large viewof the whole fusion research.

[Promotion of collaboration](7) Does the LHD project play the role of a global COE in the research with helical devices byconstructing and using the research networks among domestic and international universities
and research institutes?
Domestic network of collaboration researches is built throughout the general collaboration
research, the LHD project collaboration research, and the bilateral collaboration research, and the LHD
project is highly evaluated to play the role as domestic COE. Japan-United States, Japan-Korea, JapanChina bilateral collaboration researches are advanced actively, and international collaboration
researches are advancing under the IEA Stellarator Agreement. Therefore, the LHD project isevaluated to play the role as a international COE. It is necessary to further develop international
collaboration research strategically, to develop researches in various field by NIFS researchers as
leaders of helical fusion research, and to increase the number of international joint papers.
On the other hand, it is indispensable to visualize research networks among domestic and-8-international universities and institutes and research achievements which are created by the network,and to transmit the research achievement of universities from NIFS, as COE, for the purpose ofrevitalizing fusion research in universities.

(8) Does the LHD project promote cooperation with and contribute to ITER/BA? Further, does
the LHD project contribute to the research and development of DEMO? (From the third
mid-term plan)
It is evaluated that the LHD project makes large contributions to many research fields suchas neutron measurement, ion cyclotron emission measurement, dispersion interferometer, ICRF
oscillator, NBI, low temperature equipment, superconducting magnet of JT-60SA, inter connection
resistance conductor measurement of ITER conductor sample, and planning of JT-60SA research. Also,
three researchers from NIFS joined ITER/BA as members of QST DEMO design joint special team,and they are making large contributions.
However, it is necessity to make more effort to summarize these achievements andcontributions statistically, and to transmit the information. Furthermore, it is also necessary to havestrategic and active approaches to ITER Project and BA activities. Further contribution to researches
in accordance with the MEXT DEMO Action Plan is expected considering the commonality of DEMO
development for magnetic confinement fusion systems.

[Human Resource Development and Efforts toward Understanding by Society](9) Does the LHD project contribute to the human resource development of researchers who are
active internationally and lead the domestic and international fusion research?
It is highly evaluated that researchers who are active internationally and domestically are
fostered through LHD project research. The education of students is conducted at the Graduate
University for Advanced Studies, Department of Fusion Science, and each collaborative graduate
school. It is also highly evaluated that NIFS accepts students from various universities as special
collaborative researchers. Furthermore, NIFS accepts internship students, and the number of theinternship students is increasing yearly. They are also highly evaluated.
On the other hand, it is necessity to evaluate how much the LHD project contributes to “thehuman resource development of researchers who are active internationally and lead the domestic andinternational fusion research” based on the quantitative results. It is also necessary to give proper roles
and numerical goals to human resource development through contributions from universities andcollaboration research, and to lead the effort to make the necessary effort for realization.

-9-(10) Does the LHD project cooperate with local governments and engage in deepening theunderstanding of the deuterium experiments by local residents? Does the project also
contribute to achieving a broad social understanding of fusion research?
The cooperation through the periodic explanation meetings with three local cities and Gifu
Prefecture, NIFS Safety Inspection Committee which is jointly established by local governments, and
NIFS Deuterium Experiment Safety Evaluation Committee which are organized by outside leaders
including local governments as observers, collaboration research with Toki City Plasma ResearchCommittee, development of satellite-telephone system with local governments, and establishment ofLocal Community Cooperation Office, are highly evaluated. Additionally, the cooperation with local
governments and efforts to gain understanding of the local residents¥ for implementing the deuterium
experiment¥ such as acceptance of NIFS facility tour, contribution to science education, and open
meetings for local residents, are highly evaluated. “Public Relations Committee” is established, andconducts public relations activities cooperating with Public Relations Enhancement Task Group of the
Research Enhancement Strategy Office. This is also highly evaluated.
On the other hand, because the outreach activities are slightly biased toward local areas, itis necessity to conduct public relations activities about the significance and perspective of fusion
research by widely extending the target area. It is desirable to establish an outreach headquarters
cooperating with QST and universities based on the public relation activities NIFS has conducted, andto take leadership in such activities.

[ 2 ] Recommendations
In the present evaluation, we discussed the LHD project in NIFS. Based upon the contentsof the discussion, we describe the recommendations regarding the future plan of the LHD project
below.

(1) Systematic research regarding isotope effect in torus plasma including helical system isdramatically enhanced by the LHD deuterium experiments. It is desirable to accumulate data andgain academic understanding continuously, and to build up the fusion science research field
which can present a quantitative prospect of the research progress.

(2) LHD project should undertake the new development of the LHD project strenuously based on
results of the deuterium plasma experiment. In particular, it is necessity to accelerate thedevelopment of the steady-state research plan that encompasses the physical and engineering- 10 -

perspective taking advantage of the steady-state sustainment of high temperature plasma which is
the most important features of the LHD.

(3) It is expected to examine the development scenarios for the Helical type fusion reactor which is
attractive as a steady-state system. In addition to extracting research topics related to fusion
reactors, it is desirable to promote comprehensive research including previous reactor engineeringresearch results.

(4) Regarding the safety measures, it is required to maintain the current safe experimental environment
with due consideration to tritium remaining in the LHD and especially the appropriate managementof radiation protection for workers in the vacuum vessel. As such, it is desirable to conduct reviewsof necessary matters on a constant basis and devise rational and sustainable safety management
systems with progress in technology and the sophistication of knowledge.

(5) It is necessary to have a strategic approach to ITER Project and BA activities, and to set sight on
the commonality of the DEMO development and make contributions to research and developmentin accordance with MEXT Action Plan for the DEMO development, as well. Also, it is necessary
to make more effort to summarize the achievements and contributions regarding the ITER Projectand BA activities statistically, and to transmit information.

(6) It is desirable to lead outreach activities strategically with cooperating with QST and universities
in order to develop the public relations activities which NIFS has conducted, and to conduct public
relations activities focusing on the significance of fusion research and future perspective
nationwide.

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Chapter 3 In Closing
Since 2010, in order to further strengthen the centripetal power of NIFS as a COE in thefield of plasma and fusion research we have organized three research projects, these being LHD, theory
and simulation, and reactor engineering. Looking forward toward achieving the fusion reactor, NIFS
has initiated research programs that will integrate these research results. Moreover, the research
structure at NIFS was reorganized and all academic researchers have now been placed in one research
department. They may now participate in any or all of the three research projects by their choice. Dueto this, we anticipate the promotion of links with LHD, theory and simulation, and fusion engineering,
and we anticipate being able to respond resourcefully to new topics.
In the NIFS External Peer Review Committee review, in 2015 the Numerical Simulation
Reactor Research Project, in 2016 the Collaborative Research, and in 2017 the Reactor Engineering
Research Project were evaluated. Thus, in this current year of 2018 the Advisory Committee undertook
an external evaluation that focused on “The LHD Project.” The External Peer Review Committee wascomposed of the members of the Advisory Committee outside of NIFS and three members from abroad,and, as the experts, two members outside of NIFS and one member from abroad.

[Evaluation points in External Peer Review in Fiscal Year 2018][Implementation system and the state of implementation](1) Is the implementation system designed to achieve deuterium experiments coordinating
domestic and international researchers? (From the third mid-term plan)(2) Are the preparations of safety management equipment and of facilities and theircountermeasures done appropriately for starting the deuterium experiments? Was the safety
management system built as planned? (From the third mid-term plan)[Results of initial experiments and future research development](3) Does the LHD project obtain high-performance plasma by the deuterium experiments andproduce excellent research achievements with high academic value?

(From the third mid-term plan)(4) Does the LHD project obtain prospects for development of academic research toward acomprehensive understanding of toroidal plasmas? (From the third mid-term plan)(5) Is preparation of necessary devices and facilities for the main device, heating systems,
diagnostics, and others advanced appropriately according to the research plan of the deuterium
experiments?
(6) Will the LHD project consider further research development towards the realization of a fusion
reactor based on the achievements of the LHD project?

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[Promotion of collaboration](7) Does the LHD project play the role of a global COE in the research with helical devices byconstructing and using the research network among domesticuniversities, international
universities, and research institutes?
(8) Does the LHD project promote cooperation with and contribute to ITER/BA? Further, does the
LHD project contribute to the research and development of DEMO? (From the third mid-term
plan)[Human Resource Development and Efforts toward Understanding by Society](9) Does the LHD project contribute to the human resource development of researchers who are
active internationally and lead the domestic and international fusion research?
(10) Does the LHD project cooperate with local governments and engage in deepening theunderstanding of the deuterium experiments by local residents? Does the project also
contribute to achieving a broad social understanding of fusion research?

The External Peer Review Committee was convened four times from September 2018
through February 2019 including the e-mail discussion committee. Detailed explanations of theevaluation topics were provided from NIFS and active discussions were held. The External Peer
Review Committee members summarize evaluation results based on discussion at the committee andsubmit this report.

As the result of the external evaluation of the “LHD Project,” in general, a recommendationof an exceedingly high evaluation and a high evaluation are received for all of the above evaluation
points. Especially building of implementation system with coordinating domestic and international
researchers, preparation of safety management equipment and facilities, and building of safety
management system, and furthermore, the effort to engage in deepening the understanding of thedeuterium experiments by local residents, in particular for starting the deuterium experiments, arehighly evaluated. Therefore, we pay respect to NIFS for their sincere effort for the deuterium
experiment. The LHD project obtains high-performance plasma by the deuterium experiments steadily.
Contribution to comprehensive understanding of toroidal plasmas including the helical type are made.
They are also highly evaluated. On the other hand, it is difficult to say that further researchdevelopment towards the realization of a fusion reactor is highly evaluated at this moment. As
mentioned in the recommendation, in addition to undertaking the new development of the LHD project
strenuously taking advantage of the steady-state sustainment of high temperature plasma which is themost important feature of the helical type, it is expected to extract research topics toward the steady-- 13 -

state helical fusion reactor, and to construct the development scenarios.

In conclusion, we suggest the following recommendations regarding the future plan of the
LHD project.

(1) Systematic research regarding isotope effect in torus plasma including helical system isdramatically progressed by the LHD deuterium experiments. It is desirable to accumulate data andgain academic understanding continuously, and to build up the fusion science research field which
can present a quantitative prospect.

(2) LHD project should undertake the new development of the LHD project strenuously based on
results of the deuterium plasma experiment. In particular, it is necessary to accelerate thedevelopment of the steady-state research plan that encompasses the physical and engineering
perspective taking advantage of the steady-state sustainment of high temperature plasma which
are the most important feature of the LHD.

(3) It is expected to examine the development scenarios for the Helical type fusion reactor which is
attractive as a steady-state system. In addition to extracting research topics related to fusion
reactors, it is desirable to promote comprehensive research including previous reactor engineeringresearch results.

(4) Regarding the safety measures, it is required to maintain the current safe experimental environment
with due consideration on tritium remaining in the LHD and especially the appropriate
management of radiation protection for workers in the vacuum vessel. As such, it is desirable toconduct reviews of necessary matters on a constant basis and devise rational and sustainable safety
management system with progress in technology and sophistication of knowledge.

(5) It is necessary to have a strategic approach to the ITER Project and the BA activities, and to set
sights on the commonality in the DEMO development and make contributions to research anddevelopment in accordance with MEXT Action Plan for DEMO development as well. Also, it isnecessary to make more effort to summarize the achievements and the contributions about the
ITER Project and BA activities statistically, and to transmit the information.

(6) It is desirable to lead outreach activities strategically with cooperating with QST and universities
in order to develop the public relations activities which NIFS has conducted, and to conduct public
relations activities regarding the significance of fusion research and future perspective nationwide.

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Documents

1. 2018 External Peer Review Presentation Materials

LHD Project2018 NIFS External Review (Nagoya, Dec. 1, 2018)

1

Objectives of LHD project
LHD started its operation in 1998 to realize high performance reactor relevant plasma
in heliotron configuration, clarifying the underlying physics and engineering issues
In the “orange book” published in 1989, main objectives of LHD is shown, as follow,(1) Realize plasma with a high fusion triple product and conduct extensive
confinement study, which can be extrapolated to a fusion reactor(2) Realize beta exceeding 5 % and explore related physics.
(3) Employ divertor, conduct long pulse experiment and accumulate basic data forsteady state operation.
(4) Investigate high energy particles in helical fields and conduct simulation
experiment of alpha particles in a reactor plasma.
(5) Conduct complementary study to tokamak and deepen comprehensive
understanding of toroidal plasmas.
target:nWT䠖 <T> = 3-4 keV, <n> = 1㽢1020 m-3, WE = 0.1-0.3s
Ti (0) = 10 keV with <n> = 2㽢1019 m-3<E>Ӎ5%, B = 1-2 T

2Physics, progressed
LHD has demonstrated potential of heliotron
x thermal transport in LHD presents gyro-Bohm naturex observation of non-local transport
x operational regime and path to achieve high beta plasmax 3-d effect on- transport (viscosity) => neoclassical, turbulent (zonal flow)- MHD stability (magnetic topology) => island- edge (stochastic region) => detachment, ELM control
(m)
5
10
4
10
3
10
2
10
101

x edge heat and particle control with divertor- etc.
3

What is expected in deuterium experiment
Devicecountry

improvement
factor

JFT-2MJapan

1.1 – 1.4

JT-60UJapan

1.2 – 2

Alcator-C

USA

1.5

DIII-DUSA

1.4 – 2

ISX-B

USA

1.4

TFTR

USA

1.2

ASDEX

Germany

1.3 – 2ASDEX-U

Germany

1.5

TEXTOR

Germany

1.4

JET

EU

1.2 – 1.4

FTU

Italy

1.4

Confinement improvement by afactor of ~ 1.4 was observed indeuterium experiment in many
tokamaks.
However, little improvement
has been seen insmall/medium helical devices.
Obvious improvement is
expected in LHD with divertor

4

Objectives of the LHD deuterium experiment
LHD should demonstrate potential of the helical reactor
1. Achievement of high-performance plasmas through confinement
improvement
9 Scientific research in more reactor-relevant conditions
2. Clarification of isotope effect on confinement
9 Long-standing mystery in world fusion research
9 Needs to be understood towards burning plasma
3. Demonstration of confinement capability of energetic ions inhelical systems
9 Perspectives towards helical reactor
4. Enhanced PWI studies using hydrogen isotopes
9 Global particle balance

5

Annual Plan for LHD Deuterium ExperimentFirst 6 years

Second 3 years

FY

1st year

2nd – 6th year

7th – 9th year

After
10th year

Experiments

Preliminary Exp.
(Commissioning)

Plasma Exp. For
Target Parameters

Integrated HighPerformance Exp.

Post-LHD
Project

5.55x1010 Bq (1.5 Ci)(Integrated yield)---

Maximum
Annual Yield of
Tritium
Maximum
AnnualDischarge of
Tritium
Maximum
Annual Yield ofNeutron

3.7x1010 Bq (1 Ci)(Integrated yield)

3.7x109 Bq (0.1 Ci) (Integrated yield)

2.1x1019(Integrated yield)

3.2x1019(Integrated yield)

---

---

6

Parameters, achieved
LHD extended its operational regime with D plasmaTi

10 keV (ne = 1.3 u1019 m-3)Te

20 keV (2.0 u1018 m-3)
10 keV (1.6 u1019 m-3)

ne

1.2u1021m-3 (Te = 0.25 keV)

E

5.1 % (BT = 0.425 T)
4.1 %(1.000 T)'t
duration

54min. 28sec(0.5MW, 1keV, 4.0u1018m-3)
47min. 39sec. 3.36GJ(1.2MW, 2keV, 1.2u1019m-3)

7

Recommendations in the External Evaluation Review 2014
(1) Referencing improvement of confinement that is accompanied by the
deuterium experiment and the preparation of both heating devices anddiagnostic equipment, through deepening further discussion of concrete
experiment planning formulation together with enhancing modeling we
anticipate that this will contribute to a comprehensive understanding of
toroidal plasma. We anticipate further continuation and support of research
networks throughout Japan that focus on neutron diagnostics, tritium
recovery, and plasma-wall interaction constructed through joint research
aimed at the deuterium experiment.
㔜Ỉ⣲ᐇ㦂䛻క䛖㛢䛨㎸䜑ᨵၿཬ䜃ຍ⇕ᶵჾ䜔ィ ᶵჾ䛾ᩚഛ䜢㋃䜎䛘䚸ලయⓗ䛺ᐇ㦂ィ⏬⟇ᐃ䛻ྥ䛡䛯㆟ㄽ䜢᭦䛻῝䜑䜛䛸䛸䜒䛻䝰䝕䝸䞁䜾䜢඘ᐇ䛥䛫䜛䛣䛸䛻䜘䜚䚸䝖䝻䜲䝎䝹䝥䝷䝈䝬䛾ໟᣓⓗ⌮ゎ䛻㈉⊩䛩䜛䛣䛸䜢ᮇᚅ䛩䜛䚹㔜Ỉ⣲ᐇ㦂䛻ྥ䛡䛯ඹྠ◊✲䛻䜘䜚ᙧᡂ䛥䜜䛯୰ᛶᏊィ 䚸䝖䝸䝏䜴䝮ᅇ཰䚸䝥䝷䝈䝬ቨ┦஫స⏝➼䛾඲ᅜⓗ䛺◊✲䝛䝑䝖䝽䞊䜽䜢௒ᚋ䜒⥅⥆䞉⥔ᣢ䛩䜛䛣䛸䜢ᮇᚅ䛩䜛䚹

8

Recommendations in the External Evaluation Review 2014

(2) To begin the deuterium experiment on schedule, and under the Division of
Deuterium Experiments Management, we anticipate completion without delayof the formulation of preparation implementation planning, the preparation ofequipment, the improvement of facilities, and the establishment of the safety
management system, all of which are aimed at the deuterium experiment.
㔜Ỉ⣲ᐇ㦂䜢ᙜึ䛾ணᐃ㏻䜚䛻㛤ጞ䛩䜉䛟䚸᪂䛯䛻タ⨨䛥䜜䛯㔜Ỉ⣲ᐇ㦂᥎㐍ᮏ㒊䛾ୗ䛷䚸㔜Ỉ⣲ᐇ㦂䛻ྥ䛡䛯ᩚഛᐇ᪋ィ⏬䛾⟇ᐃ୪䜃䛻タഛ䛾ᩚഛ䚸᪋タ䛾ᨵಟ䚸Ᏻ඲⟶⌮యไ䛾☜❧➼䜢㐜ᘏ䛺䛟᏶஢䛥䛫䜛䛣䛸䜢ᮇᚅ䛩䜛䚹

9

Recommendations in the External Evaluation Review 2014

(3) NIFS has the standing as an inter-university research institute thatsummarizes research in fusion studies at universities, and succeeding safely
in completing the deuterium experiment is extremely important. In particular,
while respecting laws and regulations, respecting the opinions of local
residents, and maintaining an awareness of a good balance of academic
development, it is important to respond flexibly. Further, regarding the actual
safety management, it is expected that the appointment period for supervisors
will be overlapped and that new supervisors will be appointed appropriately,
and that this will proceed politely and steadily.
᰾⼥ྜ⛉Ꮫ◊✲ᡤ䛿኱Ꮫ䛻䛚䛡䜛᰾⼥ྜ⛉Ꮫ䛾◊✲䜢ྲྀ䜚䜎䛸䜑䜛❧ሙ䛷䛒䜚䚸㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻ᡂຌ⿬䛻᏶⤖䛩䜛䛣䛸䛿䛝䜟䜑䛶኱ษ䛷䛒䜛䚹≉䛻䚸ἲ௧䛾㑂Ᏺ䚸ᆅඖ䛾ពぢ䛾ᑛ㔜䚸Ꮫ⾡䛾Ⓨᒎ䛾䝞䝷䞁䝇Ⰻ䛔ឤぬ䜢⥔ᣢ䛧䛺䛜䜙䚸ᰂ㌾
䛻ᑐᛂ䛧䛶䛔䛟䜉䛝䛸ᛮ䜟䜜䜛䚹䜎䛯ᐇ㝿䛾Ᏻ඲⟶⌮䛻㛵䛧䛶䛿䚸୺௵⪅䛾㑅௵ᮇ㛫䜢㔜」䛥䛫㐺ษ䛻஺௦䛩䜛䛺䛹䚸୎ᑀ䛛䛴ሀᐇ䛻㐍䜑䜛䛣䛸䛜ᮃ䜎䜜䜛䚹

10

Recommendations in the External Evaluation Review 2014

(4) We can highly evaluate NIFS’ explanations for local residents andcooperation activities with local governing bodies over these many years.
From now, through achieving safety management and constant effort, it ishoped that this endeavor will gain understanding and support for fusion.
᰾⼥ྜ⛉Ꮫ◊✲ᡤ䛜㛗ᖺ䛻䜟䛯䛳䛶⾜䛳䛶䛝䛯ᆅඖᕷẸ䜈䛾ㄝ᫂䚸⮬἞య䛸䛾㐃ᦠάື䜈䛾ດຊ䛿㧗䛟ホ౯䛷䛝䚸௒ᚋ䜒Ᏻ඲⟶⌮䛻ᑐ䛩䜛ᐇ⦼䛸୙᩿䛾
ᐇ㊶䜢㏻䛨䛶䚸᰾⼥ྜ䛻ᑐ䛩䜛⌮ゎ䛸ᨭ᥼䜢ᚓ䜛䜉䛟ົ䜑䜛䛣䛸䛜ᮃ䜎䜜䜛䚹

11

Issues for Evaluation (1)(Implementation system and the state of implementation)䠄ᐇ᪋యไ䞉ᐇ᪋≧ἣ䠅

1. Is the implementation system built to achieve deuterium experimentswith coordinating domestic and international researchers?
(From the third mid-term plan)ᅜෆእ䛾◊✲⪅䜢ྲྀ䜚䜎䛸䜑䛶㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛యไ䛜ᵓ⠏䛥䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

2. Is preparations of safety management equipment and of facilities andtheir countermeasures done appropriately for starting the deuterium
experiments? Was the safety management system built as planned?
(From the third mid-term plan)㔜Ỉ⣲ᐇ㦂䛾㛤ጞ䛻䛒䛯䜚䚸Ᏻ඲⟶⌮ᶵჾ䞉タഛ➼䛾ᩚഛ䜔ᑐᛂ⟇䛜㐺ษ䛻䛺䛥䜜䜛䛸䛸䜒䛻䚸Ᏻ඲⟶⌮యไ䛜ィ⏬㏻䜚☜❧䛥䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅
12

Issues for Evaluation (2)(Results of initial experiments and future research development)ึᮇᐇ㦂䛾ᡂᯝ䛸௒ᚋ䛾◊✲ᒎ㛤

3.

Does the LHD project obtain high-performance plasma by the deuterium
experiments and produce excellent research achievements with highacademic value? (From the third mid-term plan)㔜Ỉ⣲ᐇ㦂䛷䝥䝷䝈䝬䛾㧗ᛶ⬟໬䛜ᅗ䜙䜜䚸Ꮫ⾡ⓗ౯್䛾㧗䛔ᡂᯝ䛜ᚓ䜙䜜䛶䛔䜛䛛䚹

4.

Does the LHD project obtain prospects for development of academic research
toward a comprehensive understanding of toroidal plasmas? (From the third
mid-term plan)⎔≧䝥䝷䝈䝬䛾⥲ྜⓗ䛺⌮ゎ䛻ྥ䛡䛯Ꮫ⾡◊✲䛾ᒎ㛤䛾ぢ㏻䛧䛜ᚓ䜙䜜䛶䛔䜛䛛䚹5.

Is preparation of necessary devices and facilities for the main device, heating
systems, diagnostics, and others advanced appropriately according to theresearch plan of the deuterium experiments?
◊✲ィ⏬䛻ᚑ䛳䛶䚸⿦⨨ᮏయ䚸ຍ⇕䚸ィ6.

䚸࿘㎶ᶵჾ䛺䛹䛾ᩚഛ➼䛜㐍䜑䜙䜜䛶䛔䜛䛛䚹Will the LHD project consider further research development towards therealization of a fusion reactor based on the achievements of the LHD project?
䝥䝻䝆䜵䜽䝖䛾ᡂᯝ䜢㋃䜎䛘䛶䚸᰾⼥ྜ⅔ᐇ⌧䛻ྥ䛡䛯௒ᚋ䛾◊✲ᒎ㛤䜢᳨ウ䛧䛶䛔䜛䛛䚹
13

Issues for Evaluation (3)(Promotion of collaboration)

7. Does the LHD project play the role of a global COE in the researchwith helical devices by constructing and using the research network
among domestic and international universities and research
institutes?
ᅜෆእ䛾኱Ꮫ䜔◊✲ᶵ㛵䛸䛾◊✲䝛䝑䝖䝽䞊䜽䛜ᵓ⠏䞉ά⏝䛥䜜䚸䝦䝸䜹䝹ᆺ⿦⨨◊✲䛻䛚䛡䜛ᅜෆእ䛾COE䛸䛧䛶䛾ᙺ๭䜢ᯝ䛯䛧䛶䛔䜛䛛䚹8

Does the LHD project promote cooperation with and contribute to
ITER/BA? Further, does the LHD project contribute to the researchand development of a reactor? (From the third mid-term plan)
ITERィ⏬䞉BAάື䛸䛾㐃ᦠ䚸㈉⊩䛜⾜䜟䜜䛶䛔䜛䛛䚹䜎䛯䚸ཎᆺ⅔◊✲㛤Ⓨ䛻ᐤ୚䛧䛶䛔䜛䛛䚹
14

Issues for Evaluation (4)(Human Resource Development andEfforts toward Understanding by Society)ேᮦ⫱ᡂ䚸♫఍䛾⌮ゎ䜈ྥ䛡䛯ྲྀ䜚⤌䜏

9. Does the LHD project contribute to the human resource developmentof researchers who are active internationally and lead the domestic
and international fusion research?
ᅜෆእ䛾᰾⼥ྜ◊✲䜢≌ᘬ䛧䚸ᅜ㝿ⓗ䛻䜒ά㌍䛩䜛ேᮦ䛾⫱ᡂ䛻㈉⊩䛧䛶䛔䜛䛛䚹

10. Does the LHD project cooperate with local governments and engage indeepening the understanding of the deuterium experiments by local
residents?
⮬἞య䛸䛾㐃ᦠ䜢ᅗ䜛䛸䛸䜒䛻䚸㔜Ỉ⣲ᐇ㦂䛻ᑐ䛩䜛ᆅᇦఫẸ䛾⌮ゎ䜢῝䜑䜛ྲྀ⤌䜏䜢⾜䛳䛶䛔䜛䛛䚹

15

IMPLEMENTATION SYSTEM AND
THE STATE OF IMPLEMENTATION
16

Issues for Evaluation (1)¾ Implementation system and the state of implementation䠄ᐇ᪋యไ䞉ᐇ᪋≧ἣ䠅

1. Is the implementation system built to achieve deuterium experimentswith coordinating domestic and international researchers? (From thethird mid-term plan)ᅜෆእ䛾◊✲⪅䜢ྲྀ䜚䜎䛸䜑䛶㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛యไ䛜ᵓ⠏䛥䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

2Is preparations of safety management equipment and of facilities andtheir countermeasures done appropriately for starting the deuterium
experiments? Was the safety management system built as planned?
(From the third mid-term plan)17

LHD project collaboration system
LHD experiment is governed by LHD experiment board which consistsof division directors, topical group leaders, directors of engineering
divisions.
Collaboration
research committee
Evaluation (under NIFS steeringcommittee)
Planning andcoordination
Fusionengineeringresearch
project

Numerical
simulation
reactor research
project• Research outcome• Presentation

Domestic collaborators

Proposals on
collaborations (budget)

LHD project

LHD exp. board
Planning andcoordination

International
collaborators

LHD-IPC
Operation, safety
management
ManualTopical groups
18Topical groups and leaders
May 23, 2018
Topical Group

NIFS

Universities*Hiromi TAKAHASHI
Kiyofumi MUKAI,High performance plasma

Collaborating with
Tatsuya KOBAYASHI, Kenji TANAKA,
Suguru MASUZAKI, Yasuhiro SUZUKI*Sadayoshi MURAKAMI (Kyoto University)
Akira EJIRI (University of Tokyo)

Transport and confinement*Kenji TANAKA
Mikiro YOSHINUMA
Tohru TSUJIMURA*Shigeru INAGAKI (Kyushu University)
Shinsuke OHSHIMA (Kyoto University)

Edge, divertor, atomic andmolecular processes*Suguru MASUZAKI
Chihiro SUZUKI
Tetsutaro OISHI*Mizuki SAKAMOTO (University of Tsukuba)
Hirohiko TANAKA (Nagoya University)

High beta, MHD, energetic
particles*Yasuhiro SUZUKI
Kunihiro OGAWA
Yoshiro NARUSHIMA*Kazunobu NAGASAKI (Kyoto University)
Takumi ONCHI (Kyushu University)*Principal
19

LHD International Program Committee (LHD-IPC)
To enhance the international collaboration on LHD, LHD-IPC was established,
and first meeting was held in Kyoto in Oct. 2016
June 6, 2018
Overseas
X. Duan (SWIP)
P. Gohil (GA)
C. Hidalgo (CIEMAT)W. Heidbrink (UC Irvine)
L. Hu (ASIPP)
H.K. Park (NFRI)
B. Pégourié (CEA/IRFM)
Maria-Ester Puiatti (RFX)
U. Stroth (IPP-Garching)
R. Wolf (IPP-Greifswald)
M. Zarnstorff (PPPL)
1st: Kyoto (Oct. 21, 2016) 21
2nd: Kyoto (Oct. 4, 2017) 16+4
3rd: NIFS (Sep. 19, 2018) 15+8

LHD board members
T. Morisaki
M. Osakabe
S. KuboS. Sakakibara
Topical Group Leaders (2018-2019 campaign)
H. Takahashi (NIFS)
S. Murakami (Kyoto U.)
K. Tanaka (NIFS)
S. Inagaki (Kyushu U.)
S. Masuzaki (NIFS)
M. Sakamoto (U. Tsukuba)
Y. Suzuki (NIFS)
K. Nagasaki (Kyoto U.)䝥䝷䝈䝬ⱝᡭኟ䛾Ꮫᰯ
20ᖹᡂ㻞㻞ᖺ㻤᭶㻝㻝᪥ භ⏥䝇䜹䜲䞂䜱䝷International Workshop on LHD Deuterium Experiment

21

Information transmission for LHD experiment
English portal site for LHD experiment is open for collaborators, by which one canget, e.g., machine time allocation table, daily/weekly schedule, daily report,
specifications of diagnostics, heating devices, etc.

䝥䝷䝈䝬ⱝᡭኟ䛾Ꮫᰯ22ᖹᡂ㻞㻞ᖺ㻤᭶㻝㻝᪥ᖹᡂ㻞 㻞 ᖺ㻤 ᭶භ⏥䝇䜹䜲䞂䜱䝷

Issues for Evaluation (1)¾ Implementation system and the state of implementation(1) Is the implementation system built to achieve deuterium experimentswith coordinating domestic and international researchers? (From thethird mid-term plan)(2) Is preparations of safety management equipment and of facilities andtheir countermeasures done appropriately for starting the deuterium
experiments? Was the safety management system built as planned?
(From the third mid-term plan)㔜Ỉ⣲ᐇ㦂䛾㛤ጞ䛻䛒䛯䜚䚸Ᏻ඲⟶⌮ᶵჾ䞉タഛ➼䛾ᩚഛ䜔ᑐᛂ⟇䛜㐺ษ䛻䛺䛥䜜䜛䛸䛸䜒䛻䚸Ᏻ඲⟶⌮యไ䛜ィ⏬㏻䜚☜❧䛥䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

23

Schedules of device upgrades,
modification and installation for Deuterium Experiment
FY2012FY2013

FY2014FY2015㻝㻣㼠㼔 㻯㼍㼙㼜㼍㼕㼓㼚㻔㻴㼥㼐㼞㼛㼓㼑㼚㻕㻝㻤㼠㼔 㻯㼍㼙㼜㼍㼕㼓㼚䠄㻴㼥㼐㼞㼛㼓㼑㼚䠅

FY2016FY2017

㻞㻜㼠㼔 㻯㼍㼙㼜㼍㼕㼓㼚䠄㻰㼑㼡㼠㼑㼞㼕㼡㼙㻖䠅㻝㻥㼠㼔 㻯㼍㼙㼜㼍㼕㼓㼚䠄㻴㻛㻰㼑㼡㼠㼑㼞㼕㼡㼙㻖㻕㻸㼑㼓㼍㼘㻌㻸㼕㼏㼑㼚㼟㼑㼟㻌㼒㼛㼞㻌㻸㻴㻰㻌㻰㼑㼡㼠㼑㼞㼕㼡㼙㻌㻱㼤㼜㻚㻹㼛㼐㼕㼒㼕㼏㼍㼠㼕㼛㼚㻌㼛㼒㻌㻮㼡㼕㼘㼐㼕㼚㼓㻌㼒㼛㼞㻌㻸㼑㼓㼍㼘㻌㻾㼍㼐㼕㼍㼠㼕㼛㼚㻌㻯㼛㼚㼠㼞㼛㼘㻌㻭㼞㼑㼍

Legal Inspection㼁㼜㼓㼞㼍㼐㼑㻌㼛㼒㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻔㻺㼑㼡㼠㼞㼛㼚㻌㻰㼍㼕㼓㼟㻚㻘㻌㻴㻛㻰㻌㻰㼕㼍㼓㻚㻘㻌㼑㼠㼏㻕㻹㼛㼐㼕㼒㼕㼏㼍㼠㼕㼛㼚㻌㼛㼚 㻼㼑㼞㼕㼜㼔㼑㼞㼍㼘㻌㼁㼠㼕㼘㼕㼠㼕㼑㼟㻔㻳㼍㼟㻙㼜㼡㼒㼒㻚㻘㻌㻵㻯㻱㻙㼜㼑㼘㼘㼑㼠㻘㻌㼍㼚㼐㻌㻯㼛㼛㼘㼕㼚㼓㻌㼣㼍㼠㼑㼞㻌㼟㼥㼟㼠㼑㼙㻘㻌㼑㼠㼏㻕㻵㼚㼟㼠㼍㼘㼘㼍㼠㼕㼛㼚㻌㼛㼒 㻿㼍㼒㼑㼠㼥㻌㻹㼍㼚㼍㼓㼑㼙㼑㼚㼠㻌㻰㼑㼢㼕㼏㼑㼟㻔㻱㼤㼔㼍㼡㼟㼠㻌㻰㼑㼠㼞㼕㼠㼕㼍㼠㼕㼛㼚 㻿㼥㼟㼠㼑㼙㻘㻌㻭㼏㼏㼑㼟㼟㻌㻯㼛㼚㼠㼞㼛㼘㻌㻿㼥㼟㼠㼑㼙䠅㻵㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㻌㼛㼚㻌㻿㼍㼒㼑㼠㼥㻌㻹㼍㼚㼍㼓㼑㼙㼑㼚㼠㻌㻿㼥㼟㼠㼑㼙㻘㻌㻼㼞㼑㼜㼍㼞㼍㼠㼕㼛㼚㻌㼛㼒㻌㻿㼍㼒㼑㼠㼥㻌㻻㼜㼑㼞㼍㼠㼕㼛㼚㻌㻹㼍㼚㼡㼍㼘㼟㻌㼍㼚㼐㻌㼀㼞㼍㼕㼚㼕㼚㼓㻌㻯㼛㼡㼞㼟㼑㻌

Commissioning for D-exp.

㼁㼜㼓㼞㼍㼐㼑㻌㼛㼒㻌㻴㼑㼍㼠㼕㼚㼓㻌㻰㼑㼢㼕㼏㼑㼟㻔㻌㻺㻮㻵㻌㼡㼜㼓㼞㼍㼐㼑㼟㻘㻌㻱㻯㻴㻌㼘㼍㼡㼚㼏㼔㼑㼞㻌㼕㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㼟㻘㻌㼑㼠㼏㻕㻌

Legal Inspection㼁㼜㼐㼍㼠㼑㻌㼛㼒㻌㻸㼑㼓㼍㼘㻌㻸㼕㼏㼑㼚㼟㼑㻔㻝㼟㼠 㼣㼍㼘㼘㻌㼙㼍㼠㼑㼞㼕㼍㼘㻌㻕㻵㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㻌㼛㼒㻌㻵㼚㻙㼢㼑㼟㼟㼑㼘㻌㼏㼛㼙㼜㼛㼚㼑㼚㼠㼟㻌㻔㻌㻯㼘㼛㼟㼑㼐㻌㻴㼑㼘㼕㼏㼍㼘㻌㻰㼕㼢㼑㼞㼠㼑㼞㻘㻌㼃㻙㼏㼛㼍㼠㼑㼐㻌㻰㼕㼢㼑㼞㼠㼑㼞㻘㻌㼑㼠㼏㻕㻌㻔㻌㻯㼘㼛㼟㼑㼐㻌㻴㼑㼘㼕㼏㼍㼘㻌㻰㼕㼢㼑㼞㼠㼑㼞㻘㻌㻺㻮㻵㻌㻒㻌㻱㻯㻴㻌㼏㼛㼡㼚㼠㼑㼞㻌㼣㼍㼘㼘㼟㻌㼑㼠㼏㻕㻌In-situ calibration of NFM

Conclusion of Agreement㻵㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㻌㼛㼒㻌㻵㼚㻙㼢㼑㼟㼟㼑㼘㻌㼏㼛㼙㼜㼛㼚㼑㼚㼠㼟㻌

FY2018(㼁㼜㼓㼞㼍㼐㼑㻌㼛㼒㻌㻴㼑㼍㼠㼕㼚㼓㻌㻰㼑㼢㼕㼏㼑㼟㻱㻯㻴㻌㼘㼍㼡㼚㼏㼔㼑㼞㻌㼕㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㼟㻘㻌㻡㻠㻚㻡㻛㻡㻢㻳㻴㼦㻌㻳㼥㼞㼛㼠㼞㼛㼚㻘 㼑㼠㼏)㼁㼜㼓㼞㼍㼐㼑㻌㼛㼒㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻔㻌㻱㻯㻱㻵㻘㻌㻲㼍㼟㼠㻙㼀㼔㼛㼙㼟㼛㼚㻘㻌㻌㼑㼠㼏㻕㻹㼛㼐㼕㼒㼕㼏㼍㼠㼕㼛㼚㻌㼛㼚㻌㻼㼑㼞㼕㼜㼔㼑㼞㼍㼘㻌㼁㼠㼕㼘㼕㼠㼕㼑㼟㻔㻳㼍㼟㻙㼜㼡㼒㼒㻚㻌㼍㼚㼐㻌㻯㼛㼛㼘㼕㼚㼓㻌㼣㼍㼠㼑㼞㻌㼟㼥㼟㼠㼑㼙㻌㼑㼠㼏㻕㻵㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㻌㼛㼚㻌㻿㼍㼒㼑㼠㼥㻌㻹㼍㼚㼍㼓㼑㼙㼑㼚㼠㻌㻰㼑㼢㼕㼏㼑㼟 㻔㻱㼚㼢㼕㼞㼛㼚㼙㼑㼚㼠㼍㼘㻌㻺㼑㼡㼠㼞㼛㼚㻌㻰㼛㼟㼑㻌㻹㼛㼚㼕㼠㼛㼞㻘㻌㻾㼍㼐㼕㼍㼠㼕㼛㼚㻌㻭㼞㼑㼍㻌㻹㼛㼚㼕㼠㼛㼞㻘㻌㼑㼠㼏㻕㻵㼙㼜㼞㼛㼢㼑㼙㼑㼚㼠㻌㼛㼚㻌㻹㼍㼚㼡㼍㼘㼟㻌㼍㼚㼐㻌㼀㼞㼍㼕㼚㼕㼚㼓㻌㻯㼛㼡㼞㼟㼑
24*Hydrogen operation is performed during the last one month of D-exp.

Upgraded and newly installed devices for the LHD Deuterium Experiment
Exhaust Detritiation System

MonitorMonitorIntegrated Radiation
Monitoring System
RemoteControl

Control System

MonitorUpgrade of
Diagnostics
ECH and ICH
UpgradeMonitorMonitorStack

NBI UpgradeUpgrade of Vacuum
Pumping System
ᾛᾗᾓClosed Helical
Divertor

Legal Radiation Control
Area and Access Control
System for the Area

Neutron Diagnostics
System25

Preparation for the initiation of deuterium experiment- Deuterium experiment management division is
responsible for the preparation andimplementation of the LHD deuterium experiment.

Member list of ATFDE,
which is a successor to DEPTF- D-exp management division mainly consists ofdivision directors of NIFS, including safety-related
divisions, which enables fast decision and topdown implementation.
- Under the D-exp management division,
Deuterium Experiment Preparation Task Force(DEPTF)*, carries out the design and construction
for individual items including the safety
management, according to the planned
preparation schedule for the initiation of thedeuterium experiment.

*The DEPTF is renamed to Assistance Task Force for Deuterium Experiment26
implementation (ATFDE) after the start of LHD D-exp.

Establishment of the Legal Radiation Controlled Area (LRCA)••

Personnel access to the LRCA must
pass through the access control room.
The access is also controlled by the
personnel authentication with QR-code
at access gates placed at the entrance
room of LRCA.

LHD Hall㻭㼏㼏㼑㼟㼟㻌㻯㼛㼚㼠㼞㼛㼘㻌㻾㼛㼛㼙㻯㼛㼚㼠㼞㼛㼘 㻾㼛㼛㼙㼙㻭㻌㼜㼑㼞㼟㼛㼚㼍㼘㻌 㻽㻾㻙㼏㼛㼐㼑㻌㼞㼑㼍㼐㼑㼞㼐㼛㼟㼕㼙㼑㼠㼑㼞㻌㼣㼕㼠㼔㻌㻽㻾㻙㼏㼛㼐㼑

LHD Hall㻭㼏㼏㼑㼟㼟㻌㻯㼛㼚㼠㼞㼛㼘㻌㻾㼛㼛㼙

Access Gates
for LHD Hall㻯㼛㼚㼠㼍㼙㼕㼚㼍㼠㼕㼛㼚㻌㻵㼚㼟㼜㼑㼏㼠㼕㼛㼚㻌㻾㼛㼛㼙
27

Access Gates

Neutron and tritium measurements and control
Amount of neutron and tritium production must be grasped for thesafety control of deuterium experiment.
50%

T+p

50%

3He + nD+D

Number of Tritium= Number of Neutron

Tritium production rate canbe evaluated from neutron
emission rate.

Annual total neutron (tritium) yield must be smaller than 2.1x1019[n] (37[GBq)for the first 6
years, while the amount must be smaller than 3.2x1019[n] (55.5[GBq)for the last 3 years

㻺㻲㻹

㻺㻲㻹

LHD Hall

LHD Building

Control Room Building

Control Room

Weekly Total Emission
Annual Total Emission

㻺㻲㻹Radiation Monitoring Room
Digital Processing
Unit

Data Processing Server Room(1)Neutron Emission Rate
Neutron Emission/Shot

Realtime Display of
Total Neutron Emission of
the week and of the year

28/21

Calibration of Neutron Diag.
•

Prior to D-exp. an in situ neutron
calibration experiment was carried out by
using a 252Cf neutron source of 800 MBq(~1x108[n/s]) in November 2016.

•

The source was circulated in the tours
using a toy train.
FC, 3He-, and 10B -proportional counterand activation foil system (8-o) were
calibrated•

Activation Foil
252Cf-source

Fission Chamber
10B proportional counter3He proportional counter
29

Exhaust Detritation System (EDS)
Two types of exhaust detritiation system were installed.
- Molecular sieve (MS) type for exhausted gas in the vacuum pumping during plasma
experiments- Polyimide membrane (PM) type for purged gas in the maintenance
Stack

EDS
Catalytic
recombinersr

Molecular sieveMdriers

Q2, CxQy+O2ĺQ2O[Q: H, D, T]

All Peripheral Facilities
Using Vacuum Pumps

Initial specification:
operation results:
Design(Mar. 6 – May 22, 2017)
Recovery rate > 95 %Tritium
recovery[Detritiation
factor >rate20] > 99.8 %NBIs, Gas puff,
Ice pellet injector, and
Cf. > 95% (Designed)
Plasma diagnostics, etc• All of the tritium exhausted from the vacuum vessel of the peripheral facilities as30
well as LHD are monitored at the entrance of the EDS.

Legal License as a Radiation Generator and Radio Isotope Facility
and the 1st Legal Inspection¾ Application of Legal License and the approval• Application of Legal License as a radiation generator ( Jan. 7th, 2015)
9 Since the accelerator of the Heavy Ion Beam Probe (HIBP) is classified as a Legal Radiation
Generator, the application was done by adding the LHD to the License of HIBP accelerator.
• Approval of the application (Sept. 4th ,2015)¾ Establishment of Legal Radiation Controlled Area (LRCA) Since Nov. 7, 2016 ~• 㼀㼔㼑㻌㻸㻾㻯㻭㻌㼒㼛㼞㻌㼠㼔㼑㻌㼡㼟㼑㻌㼛㼒㻌㻞㻡㻞㻯㼒㻌㼚㼑㼡㼠㼞㼛㼚㻌㼟㼛㼡㼞㼏㼑㻌㼍㼚㼐㻌㻲㻯㻌㻔㻺㼛㼢㻚㻌㻣㼠㼔㻘㻌㻞㻜㻝㻢㻌䇵 㻹㼍㼞㻚㻌㻡㼠㼔 㻘㻞㻜㻝㻣㻕
9 㻵㼙㼜㼘㼑㼙㼑㼚㼠㼍㼠㼕㼛㼚㻌㼛㼒㻌㼠㼔㼑㻌㻭㼎㼟㼛㼘㼡㼠㼑㻌㻯㼍㼘㼕㼎㼞㼍㼠㼕㼛㼚㻌㼛㼒㻌㻺㼑㼡㼠㼞㼛㼚㻌㻲㼘㼡㼤㻌㻹㼛㼚㼕㼠㼛㼞㻌㻔㻺㻲㻹㻕 㼡㼟㼕㼚㼓㻌㼍㻌㻞㻡㻞㻯㼒㻌㼚㼑㼡㼠㼞㼛㼚㻌㼟㼛㼡㼞㼏㼑㻚• 㼀㼔㼑㻌㻸㻾㻯㻭㻌㼒㼛㼞㻌㼠㼔㼑㻌㼡㼟㼑㻌㼛㼒㻌㻾㼍㼐㼕㼍㼠㼕㼛㼚㻌㻳㼑㼚㼑㼞㼍㼠㼛㼞㻌㻔㻹㼍㼞㻚㻌㻢㼠㼔 㻘㻞㻜㻝㻣㻌㻙 㻺㼛㼣㻕
9 㻵㼙㼜㼘㼑㼙㼑㼚㼠㼍㼠㼕㼛㼚㻌㼛㼒㻌㼠㼔㼑㻌㻸㻴㻰㻌㻰㼑㼡㼠㼑㼞㼕㼡㼙㻌㼑㼤㼜㼑㼞㼕㼙㼑㼚㼠¾ 1st Legal Inspection• 㻭㻌㼜㼞㼑㼘㼕㼙㼕㼚㼍㼞㼥㻌㼕㼚㼟㼜㼑㼏㼠㼕㼛㼚㻌㼠㼛㻌㼏㼔㼑㼏㼗㻌㼠㼔㼑㻌㼕㼚㼠㼑㼞㼘㼛㼏㼗㻌㼟㼥㼟㼠㼑㼙㻌㼍㼚㼐㻌㼞㼍㼐㼕㼍㼠㼕㼛㼚㻌㼟㼔㼕㼑㼘㼐㼕㼚㼓㻌㼍㼎㼕㼘㼕㼠㼥㻌㼛㼒㻌㼠㼔㼑㻌㻸㻾㻯㻭㻚㻌
9 㻼㼑㼞㼒㼛㼞㼙㼑㼐㻌㼐㼡㼞㼕㼚㼓㻌㼠㼔㼑㻌㼜㼑㼞㼕㼛㼐㻌㼛㼒㻌㼠㼔㼑㻌㻭㼎㼟㼛㼘㼡㼠㼑㻌㻯㼍㼘㼕㼎㼞㼍㼠㼕㼛㼚㻌㼛㼒㻌㻺㻲㻹㻌㻔㻺㼛㼢㻚㻌㻝㻠㼠㼔 㻙㻝㻡㼠㼔 㻘㻞㻜㻝㻢㻕㻚• 㼀㼔㼑㻌㼐㼑㼒㼕㼚㼕㼠㼕㼢㼑㻌㼕㼚㼟㼜㼑㼏㼠㼕㼛㼚㻌㼠㼛㻌㼑㼤㼍㼙㼕㼚㼑㻌㼠㼔㼑㻌㼞㼍㼐㼕㼍㼠㼕㼛㼚㻌㼟㼔㼕㼑㼘㼐㼕㼚㼓㻌㼍㼎㼕㼘㼕㼠㼥㻌㼛㼒㻌㼠㼔㼑㻌㻸㻾㻯㻭㻌㼡㼟㼕㼚㼓㻌㼠㼔㼑㻌㼚㼑㼡㼠㼞㼛㼚㻌㼜㼞㼛㼐㼡㼏㼑㼐㻌㼒㼞㼛㼙㻌㻸㻴㻰㻌㼜㼘㼍㼟㼙㼍㼟㻚
9 㻼㼑㼞㼒㼛㼞㼙㼑㼐㻌㼐㼡㼞㼕㼚㼓㻌㼠㼔㼑㻌㼏㼛㼙㼙㼕㼟㼟㼕㼛㼚㼕㼚㼓㻌㼜㼔㼍㼟㼑㻌㼛㼒㻌㻰㼑㼡㼠㼑㼞㼕㼡㼙㻌㼑㼤㼜㼑㼞㼕㼙㼑㼚㼠㻌㻔㻹㼍㼞㻚㻌㻣㼠㼔 㻙㻝㻣㼠㼔 㻘㻌㻞㻜㻝㻣㻕
9 㻺㼛㻌㼞㼍㼐㼕㼍㼠㼕㼛㼚㻌㼒㼞㼛㼙㻌㼠㼔㼑㻌㻸㻴㻰㻌㻰㻙㼜㼘㼍㼟㼙㼍㼟㻌㼣㼍㼟㻌㼐㼑㼠㼑㼏㼠㼑㼐 㼎㼥㻌㼠㼔㼑㻌㼐㼛㼟㼕㼙㼑㼠㼑㼞㼟㻌㼜㼘㼍㼏㼑㼐㻌㼖㼡㼟㼠㻌㼛㼡㼠㼟㼕㼐㼑㻌㼠㼔㼑㻌㼞㼍㼐㼕㼍㼠㼕㼛㼚㻌㼟㼔㼕㼑㼘㼐㼕㼚㼓㻌㼣㼍㼘㼘㻌㼛㼒㻌㼠㼔㼑㻌㻸㻴㻰㻌㼔㼍㼘㼘㻌㼍㼚㼐㻌㼎㼥㻌㼠㼔㼑㻌㻾㻹㻿㻭㻲㻱㻚䋻 㼀㼔㼕㼟㻌㼜㼞㼛㼢㼑㼟㻌㼟㼡㼒㼒㼕㼏㼕㼑㼚㼠㻌㼞㼍㼐㼕㼍㼠㼕㼛㼚㻌㼟㼔㼕㼑㼘㼐㼕㼚㼓㻌㼜㼑㼞㼒㼛㼞㼙㼍㼚㼏㼑㻌㼛㼒㻌㼠㼔㼑㻌㻞㼙㻙㼠㼔㼕㼏㼗㻌㻌㼏㼛㼚㼏㼞㼑㼠㼑㻌㼣㼍㼘㼘㻚

Certification for the Legal Inspection was issued for LHD on Mar. 29th, 2017.

31/21

Status of safety management facilities and system
Integrated Radiation Monitoring System (IRMS)
࣭IRMS unify the information from the access control system, radiation monitoring system(RMSAFE), and centrally controls the interlock system related to radiation safety.
э It is confirmed system works properly as designed.
э Live data from IRMS are displayed on the web.-page of.
࣭Function of the IRMS and its proper operation were checked at the 1st legal inspection.
Training exercise
9 Fire-fighting and/or evacuation drills during experiment with Toki fire-fighting team are
performed annually.
9 New training course for tritium handling in NIFS started for operators of LHD.
Constant vigil
9 IRMS and other important facilities are kept vigil by NIFS staff (researchers and engineers),
preparing for the initial troubles and accident.

Simulator in NIFS
for training on
safety handling oftritium.

Fire-fighting
drill

32

Table of manuals for deuterium experiment

These manuals are available on the web siteof Division of Health and Safety Promotion
33/21

RESULTS OF INITIAL EXPERIMENTS
AND FUTURE RESEARCHDEVELOPMENT
34

Issues of Evaluation (2)¾ Results of initial experiments and future research development(3) Does the LHD project obtain high-performance plasma by the deuterium
experiments and produce excellent research achievements with highacademic value? (From the third mid-term plan)㔜Ỉ⣲ᐇ㦂䛷䝥䝷䝈䝬䛾㧗ᛶ⬟໬䛜ᅗ䜙䜜䚸Ꮫ⾡ⓗ౯್䛾㧗䛔ᡂᯝ䛜ᚓ䜙䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(4) Does the LHD project obtain prospects for development of academic research
toward a comprehensive understanding of toroidal plasmas? (From the third
mid-term plan)⎔≧䝥䝷䝈䝬䛾⥲ྜⓗ䛺⌮ゎ䛻ྥ䛡䛯Ꮫ⾡◊✲䛾ᒎ㛤䛾ぢ㏻䛧䛜ᚓ䜙䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(3) Is preparation of necessary devices and facilities for the main device, heating
systems, diagnostics, and others advanced appropriately according to theresearch plan of the deuterium experiments?
(4) Will the LHD project consider further research development towards therealization of a fusion reactor based on the achievements of the LHD project?
35

Issues of Evaluation (2)¾ Results of initial experiments and future research development(3) Does the LHD project obtain high-performance plasma by the deuterium
experiments and produce excellent research achievements with highacademic value? (From the third mid-term plan)㔜Ỉ⣲ᐇ㦂䛷䝥䝷䝈䝬䛾㧗ᛶ⬟໬䛜ᅗ䜙䜜䚸Ꮫ⾡ⓗ౯್䛾㧗䛔ᡂᯝ䛜ᚓ䜙䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(4) Does the LHD project obtain prospects for development of academic research
toward a comprehensive understanding of toroidal plasmas? (From the third
mid-term plan)⎔≧䝥䝷䝈䝬䛾⥲ྜⓗ䛺⌮ゎ䛻ྥ䛡䛯Ꮫ⾡◊✲䛾ᒎ㛤䛾ぢ㏻䛧䛜ᚓ䜙䜜䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

These two issues (item(3) and (4)) can be satisfied by realizing the objectives of D-exp.
(3) Is preparationof necessary devices
andthroughfacilitiesconfinement
for the mainimprovement
device, heating• Achievementof high-performance
plasmassystems,ofdiagnostics,
andon
othersadvanced appropriately according to the• Clarification
isotope effectconfinement
research planof the deuterium
experiments?
• Demonstrationof confinement
capabilityof energetic ions in helical systems• Enhanced PWI studies using hydrogen isotopes(4) Will the LHD project consider further research development towards therealization of a fusion reactor based on the achievements of the LHD project?
36

Ion temperature range is extended by the D- exp.
12

2.4
Ti

2
1.6
ne

6

1.2

4

0.8

2

T

0
-0.8

-0.4

0.4
e

0
r

eff

e

8

n [x1019m3]

ie

T , T [keV]

10

0.4

0
0.8

[m]

Ti = 10 keV was achieved in helical devices for the first time. The LHD succeeded
to realize higher performance plasma in Deuterium experiment than in Hydrogenexperiments. Now, we are trying to expand temperature region to Te=Ti=8.6keV to37
explore the physics close to reactor plasma parameter.

By starting D-exp., the LHD can explore the physics on Isotope effect,
which is known to be a long-standing mystery
Isotope effect on the confinement is widely observed in Tokamak plasmas, but its
physical mechanism is not clear.
••

Empirical Scaling of isotope by ߬ா ~‫ܣ‬ఈ is often mentioned.
– The D is different in the discharge scinarios and machine.
• ITER89-P: D=0.5[1], ITERH93-P:D=0.4,• DD/DT: TFTR(supershot): D=0.85[3],JET(H-mode): D=0.03(total) (D=-0.17(core), D=0.5(pedestal))[4]Gyro-bohm scaling indicates:
D=-0.2[4](in Engineering scaling).
(in Physics Scaling: D=-0.5 as ߬ா ீ஻ ‫׽‬௔మఞಸಳand ߯ ீ஻ ~ఘమ ௏౪౞
ோ~

࢓૙.૞ ் భ.ఱ
ோ௤ మ ஻మ

)There are several mechanisms which might influence the plasma confinement property bychanging the ion species from H to D.
•••

Bulk ion species, itself <= direct effect
Neutral penetration <= Neutral recycling is widely known as a key control knob for achieving high performance
plasmas [5]Impurity influx <= The Zeff at the edge influences the H-mode pedestal performance[6].

In order to understand the mechanisms of isotope effect, the following items must be
studied in addition to the evaluation on isotope dependence of confinement time:
9 Influences of ion-species, including impurity ions, on confinement property.
9 The comparison of experimental results to theoretical investigation, i.e., turbulence simulation.
[1] P.N.Yushmanov, et.al., NF 30(1990)1999 , [2] M. Bessenrodt-weberpals, et.al., NF22(1993)1205, [3] S.D.Scott, et.al., POP 2(1995)2299 ,[4] J.Jacquinot, et.al., PPCF 41(1999)A13 , [5] C.F.Magi, et.al., IAEA-FEC 2014 EX3-3 , [6] G.P. Maddison, et.al., NF54(2014)073016

38

Global energy confinement is clearly improved in D fromH in gyro-Bohm nature
Energy confinement time in NBI plasma

H
D

-1

ି଴.଼଻±଴.଴ଵ
௦௖௟߬ா,௧௛,ே஻ூ‫ିܣ ן‬଴.଴ଵ±଴.଴ଶ ‫ܤ‬଴.଼ହ±଴.଴ଶ ݊ǉ ௘଴.଻଼±଴.଴ଵ ܲ௔௕௦

exp

(s)

10

W

E,th

(AD/AH)-0.01 = 2-0.01 = 0.99
x No significant mass dependence, which indicates clear
discrepancy from gyro-Bohm model (isotope effect)x Comparison between dimensionally similar plasmas also
indicates clear isotope effect

-2

10

-2

10

-1

W

scl

E,th

(s)

10

D

H
-1

Energy confinement time in ECH plasma
ି଴.ହଶ±଴.଴ଵ
߬ா,௧௛,ா஼ு ‫ܣ ן‬଴.ଶସ±଴.଴ଵ ݊ത ௘ ଴.ହ଼±଴.଴ଵ ܲ௔௕௦(AD/AH)0.24 = 20.24 = 1.18

-110

x Obvious mass dependence (isotope effect) identifiedWE,dia ECH

exp

(s)

5 10

2

R =0.93-1
10 scl

W

E

-1

5 10
(s)

9 Each experiment was performed with purity of H and D >80%

Isotope effect was recognized for both NBI and ECH plasmas on the LHD

39

Isotope effect is also observed for ITB plasmas
Significant isotope effect was observed both in
ion and electron heat transports

Fi/FGB in GKV

Fe/FGB in GKV

Zonal flow enhancement
was also confirmed in GKV
simulation

Reduction of Fi/FGB and Fe/FGB in D plasma werereproduced with the nonlinear GKV simulations
Comparison of turbulence levels between measurement and simulation is ongoing 40

EP confinement comparable to similar size tokamaks aredemonstrated by Triton burn-up experiment
Triton burnup experiment can examine behavior of alpha-particle
confinement in the machine. (‫(ࢀ࣋ ׶‬૚ࡹࢋࢂ) ൎ ࣋ࢻ(૜.૞ࡹࢋࢂ) )D + D => 3He + n(2.5MeV)
D + D => p + T(1 MeV)
T + D => n(14MeV) + 4He (3.5 MeV)
Max. @ 40keV(COM)(T burn-up ratio)‫ؠ‬ௌ೙ భరಾ೐ೇ

ௌ೙ మ.ఱಾ೐ೇ

• Inward-shifted configuration provides“better” EP confinement although worse
MHD stability
Rax=3.55m

Rax=3.9m• The tendency of Triton burn-up ratios well
explained by theoretical predictions
T burn-up ratio in similar size tokamaks :- TFTR~0.7%*- KSTAR~0.45%***C.Barnes, et al., NF38(1998)597, ** J. Jo, et al. RSI87(2016)11D828

Typical trapped particle orbits

41

Interactions between EPs and MHD modes
Interaction between low-frequency MHD (interchange) mode and ripple trapped Energetic
Particle, which is called as Energetic particle driven InterChange mode (EIC), was observed.
э Analogous to the FishBone mode(FB) and/or Energetic particle driven resistive Wallmode (EWM) in tokamaks.
э Comprehensive understanding on the interaction between EPs and MHD modes intoroidal devices will be provided.

(a)Change of line integrated neutron emission profile
before and after EIC measured by VNC,(b)Calculated 2D Neutron emission profile along thesight line of Vertical Neutron Camera (VNC)
42

Exhaust Behavior and Mass Balance of Tritium
Exhaust detritiation system with precise detector revealed tritium behavior in LHD•

35.5 % of produced tritium was
exhausted until the end of the first Dcampaign, and 64 % was still retained in
vacuum vessel or evacuation system
By the tritium measurement using
imaging plates at one helical section,
15.6-31.2% of produced tritium wasevaluated to be implanted into thecarbon divertor tiles.

1 10

Tritium amount [Bq]

•

10

8 10

9

6 10

9

4 10

9

2 10

9

Tritium inventory in LHD
Tritium exhaust rate:
Exhausted tritium
35.5 %

Tritium exhaust rate:
5.1 %Plasma side0
17/3/12 17/4/9

17/5/7

17/6/4

17/7/2 17/7/30

Mass balance of tritium during thefirst deuterium experimental
campaign from March 6 to August 7
VV side43

IP images and the location of measured carbon platesIssues of Evaluation (2)¾ Results of initial experiments and future research development(3) Does the LHD project obtain high-performance plasma by the deuterium
experiments and produce excellent research achievements with highacademic value? (From the third mid-term plan)(4) Does the LHD project obtain prospects for development of academic research
toward a comprehensive understanding of toroidal plasmas? (From the third
mid-term plan)(5) Is preparation of necessary devices and facilities for the main device, heating
systems, diagnostics, and others advanced appropriately according to theresearch plan of the deuterium experiments?
㔜Ỉ⣲ᐇ㦂䛾◊✲ィ⏬䛻ᚑ䛳䛶䚸⿦⨨ᮏయ䚸ຍ⇕䚸ィ䛾ᩚഛ➼䛜㐍䜑䜙䜜䛶䛔䜛䛛䚹䚸࿘㎶ᶵჾ䛺䛹ᚲせ䛺ᶵჾ(6) Will the LHD project consider further research development towards therealization of a fusion reactor based on the achievements of the LHD project?

44

Upgraded and newly installed devices for the LHD Deuterium Experiment
Exhaust Detritiation System

MonitorMonitorMonitorIntegrated Radiation
Monitoring System

Control System

Upgrade/Modificationof Diagnostics

RemoteControl
MonitorMonitorStack• H/D ratio• Spectroscopy at diverter/edge• Fast Thomson
эCollaboration with U. of Wisconsin• PCI (Phase Contrast Imaging)• DBS (Doppler Back Scattering)• ECEI (Electron Cyclotron Emission Imaging)• Material Insertion Station, …..

ECH and ICH
UpgradeNBI UpgradeUpgrade of Vacuum
Pumping System
ᾛᾗᾓClosed Helical
Divertor

Legal Radiation Control
Area and Access Control
System for the Area

Neutron Diagnostics
System• Neutron Flux Monitor• Vertical Neutron Camera• Activation Foil
• SciFi (14MeV) detector

45

To suppress the particle and impurity influx to LHD
plasmas, closed helical diverters were installed
Open Divertor
Proto-type & High performance
Cryo Pump

Proto-type Cryo Pump

Closed Divertor

Closed Diverter with Proto-type Cryo Pump
Closed Diverter with High-performance Cryo Pump
Closed Diverter without Pump + NB counter wall protection
Closed Diverter without Pump
Closed Diverter with non-evaporating Getter Pump (FY2018)

46

Operation of NBI with Deuterium
NBI#5

Positive-NBI
40keV-6MW (H)80keV-9MW(D)
Negative-NBI
180keV-5MW(H)180keV-2.5MW (D)Negative-NBI
180keV-5MW(H)180keV-2.5MW (D)Negative-NBI
180keV-5MW(H)180keV-2.5MW (D)

NBI#2

NBI#1

NBI#3
NBI#4
Positive-NBI
40keV-6MW(H)
60keV-9MW(D)- Positive-NBI: Injection energies can be increased from 40 to 60/80keV without thedeterioration of neutralization efficiency changing the beam ion species from H to D.
Negative-NBI: Injection energy remains same at 180keV. No significant optimization for Doperation is done for N-NBI. Their injection power is expected to be degraded according to theChild-Langmuir law, i.e., ‫ܫ‬௕௘௔௠ ‫ି݉ ן‬ଵΤଶ э‫ܫ‬஽ష Τ‫ܫ‬ு ష ~0.7. It is necessary to reduce the beam
current further (‫ܫ‬஽ష Τ‫ܫ‬ு ష ~0.5) due to the isotope effect on negative-ion production.
47

Upgrade of positive-ion NBI
㻝㻜㻜With the change of beam ion species
from H to D.,

㻢㻜

㼍㼏㼏

the arc efficiency of the ion source
remains same, and2.

㻴㼥㼐㼞㼛㼓㼑㼚
㻰㼑㼡㼠㼑㼞㼕㼡㼙㻤㻜㻵 㻌㻔㻭㻕

1.

㻠㻜

The proton ratio of beam also
remains same.

㻞㻜㻜

The injection power of P-NBI issuccessfully increased from 6 to 9MW.

㻜

㻞㻜

㻠㻜

㻢㻜

㻤㻜

㻝㻜㻜

㻼㼍㼞㼏㻌㻔㼗㼃㻕

㻝

㻝㻞
㻥㻹㼃

㻼㼛㼣㼑㼞㻌㼞㼍㼠㼕㼛

㻺㻮㻵㻏㻠

㻝㻜

㻺㻮㻵㻏㻡
㻤

㻼㼛㼣㼑㼞㻌㼇㻹㼃㼉-㼪㻝㻤㼠㼔㻌㼏㼥㼏㼘㼑

㻢
㻠

㻜㻚㻤
㻱㻜 㻔㻰㻕 㻔㻴㻕
㻱㻜㻛㻞
㻱㻜㻛㻟

㻜㻚㻢
㻜㻚㻠
㻜㻚㻞

㻞

㻜

㻜
㻟㻜

㻠㻜

㻡㻜

㻢㻜

㻱㼚㼑㼞㼓㼥㻌㼇㼗㼑㼂㼉

㻣㻜

㻤㻜

㻜

㻞㻜

㻠㻜

㻢㻜 㻤㻜
㻼㼍㼞㼏㻌㻔㼗㼃㻕㻝㻜㻜 㻝㻞㻜
48

The Deuterium operation of N-NBI
The arc-efficiency was reduced by afactor of 0.7 which is consistent to theprediction.

The fraction of co-extracted electron
increases with a factor of 2. (isotope effect)
эThis increases the heat load onto
the grids of the ion-source andlimits the power of the source about
the half.

80
Hydrogen

70

I

/I

acc ext

~ 0.8

1

50
e D

I /I -, I /I -

e H

40
30
20

/I

acc ext

0

100

400

P

arc

The degradation of injection power and thebeam velocity reduction in D-operation
disables the plasma initiation by N-NB.

x2
Hydrogen5~ 0.72

200
300
P [kW]

e D

0.4

0

[MW]

I

I /I e H
I /I -

0.6

0.2

Deuterium

10
0

NBI#3

0.8

inj.

I

acc

[A]

60

4
3
2

Deuterium

NBI#3
P
inj.

x 1/2

1

Hydrogen Deuterium0136500 137000 137500 138000 138500
49
LHD Shot Number

Upgraded ECH system for deuterium experiment- Three 77GHz- and two 154GHz-ECH systems, each of which injects >1MW
for a short pulse and >300kW for CW, have been installed.
- The launchers of two 77GHz- and two 154GHz-ECH systems are
replaced to 2-O port, where the better ECH absorption is expected, tomaximize the heating efficiency.
- Another ECH launcher locates at 5.5-U port.
- Additional ECH launcher is in preparation at 9-O port.
- Instead of an 82.7GHz-ECH(5.5-U) system which was used up to the 19th
cycle, 54.5/56GHz-ECH system is newly installed to enable the LHD operation
at 1T with Deuterium N-NB operation.

50

ICH antennae are tentatively removed, but will
be reinstalled for 21st campaign (FY2019).
- Each antenna injects >1MW for pulse and >0.5MW for CW.

4.5U/L FAIT antenna- 2 straps of FAIT (Field-Aligned Impedance-Transforming) antenna- 2 straps of HAS (HAsu-Seigyo) antenna with Ex-Vessel ImpedanceTransformers (EVIT)- With the benefit from Impedance Transformers, the effective
impedance of antenna are increased although it requires to operate at
the fixed frequency of 38.5 MHz.

3.5U/L HAS antenna

51

Neutron Diagnostic
Neutron diagnostic is newly installed for the LHD deuterium experiment.
Because DD-reaction rate is larger for lager relative velocity, this will
accelerates the EP confinement studies on Helical Devices
Neutron Flux Monitor (NFM)

Plasma•Neutron Flux Monitor x3•Vertical Neutron Camera•Activation Foil System•SciFi (14MeV) detector

x2

Torus hallVertical Neutron
Camerabasement

Change of line integrated neutron emission
profile with the magnetic axis location 52

Neutron Emission evaluation codes are also prepared.

Exp.
Cal.

5
4
3

13

[x10 n/s/MW]• Neutron budget is anotherconstraints in proceeding the D.exp. in addition to the totalmachine time.
• The fit3d-dd code, which is basedon Fokker-Plank model, wasprepared so that every collaborator
can quickly evaluate neutron
emission rate for his/her proposedmachine time.

Neutron Emission Rate

6

2
1
0
0

0.5

1

1.5
19

n [x10
e

2

2.5

-3

m ]

The fit3d-dd code overestimates the neutron emission rate by a factor of 2. This
comes from the model which does not account the effect of orbit loss during theslowing down process of energetic particles.

53

H/D ratio profile measurement based on an active Charge Exchange
diagnostic revealed different particle confinement property of Deuterium
ions from Hydrogen ions in the Hydrogen isotope mixture plasma althoughelectron density behave same
Transient behavior after Hydrogen/Deuterium ice pellet injection are examined.
Decay time of electron density is similar in both cases.

There are two time scales of the decay in D/(H+D) andH/(H+D) ratio
Fast decay (t < 5.29 sec)Æ Profile relaxation
Slow decay (t >5.29 sec)Æ particle confinement
H : 0.27sec and D: 0.39sec
Decay time of deuterium ion is longer than that of hydrogenÆ Better ion particle confinement in deuterium plasma 54

Diagnostics at plasma periphery/divertor region
Influence on plasma periphery by the change of plasma ion species from hydrogen to
deuterium is a great concern. To examine the influence, spectroscopy system and IR
camera at divertor regions are improved.
Carbon impurity is increased by changing H to D. This is considered CIV(465.8nm)
to be due to the increase of physical sputtering of carbon by D.

55

Issues of Evaluation (2)¾ Results of initial experiments and future research development(3) Does the LHD project obtain high-performance plasma by the deuterium
experiments and produce excellent research achievements with highacademic value? (From the third mid-term plan)(4) Does the LHD project obtain prospects for development of academic research
toward a comprehensive understanding of toroidal plasmas? (From the third
mid-term plan)(5) Is preparation of necessary devices and facilities for the main device, heating
systems, diagnostics, and others advanced appropriately according to theresearch plan of the deuterium experiments?
(6) Will the LHD project consider further research development towards therealization of a fusion reactor based on the achievements of the LHD project?
LHD䝥䝻䝆䜵䜽䝖䛾ᡂᯝ䜢㋃䜎䛘䛶䚸᰾⼥ྜ⅔ᐇ⌧䛻ྥ䛡䛯௒ᚋ䛾◊✲ᒎ㛤䜢᳨ウ䛧
䛶䛔䜛䛛䚹

56

In optimizing the Heliotron-type helical configuration, the choice of magnetic
axis location is an important issue because its direction in optimization for
the MHD stability and for the particle confinement is opposite to each other.
Small

Large

Rax

Stable

MHD
Good

Rax=3.53m(Neoclassically optimized*)

Particle Confinement

Rax=3.6m(V-optimized)

Rax=3.75m(Standard)

Rax=3.9m(Outwardly shifted)

Deviation of orbit’s drift-surfaces are minimized as the magnetic axis locations areinwardly shifted. Triton burn-up experiments clearly show the benefit ofneoclassically optimized configuration at around 3.53m.
* S.Murakami et al., Fusion Sci. Technol. 46 (2004) 241

57

Central ion temperature is peaked at around Rax~3.59m
Generally speaking, the Ti0 degrades when the Rax
becomes large.
– The degradation at Rax =3.55m can be explained by
the degradation of heating efficiency because thetangency radius of negative-ion based NBIs are set at
R=3.7/3.75m

This tendency makes sense if the bulk-ion transport isdominated by neoclassical transport.
я ߯ ௘௫௣ > ߯ ௡௘௢

Indicating a link between neoclassical transport andanmalous transport.
䖼 Typical thermal diffusivity profile
in a LHD high-Ti discharge where
thermal diffusivities evaluated by theexperiments (solid lines) is muchlarger than those by the neoclassicaltheory (dots).
Figure from K.Nagaoka et al., Fusion Sci
Technol. 46 (2004) 241

58

Global transport analysis also indicate a link between
anomalous transport and neoclassical transport.
H.Yamada et al., Nucl. Fusion 45 (2005) 1684

The confinement improvement factor (WEexp./ WEISS04),
which is the ratios of confinement times evaluated byexperiments to these estimated by the ISS04 scaling
law, seems to improve with the decrease of theeffective helical ripples (Heff), which is a measure ofneoclassical transport in helical device, i.e., smaller Heff
is better neoclassical transport in 1/Q regime.

Experimental investigation on the link between neoclassical transport
and anomalous transport is important to establish the comprehensive
understanding in toroidal plasmas in addition to the isotope effect study.
9 Comparison between the Fexp. and Fneo. for various configuration.
9 Comparison of the measured turbulence level to Fexp. and Fneo.
9 Comparison of simulated turbulence level to the measurement, e.g.,
PCI, DBS and etc.
59

In the future fusion reactor, plasmas are sustained and controlled by fusion born aparticles. Thus, realtime estimation of energetic particle profiles will be necessary. For
this purpose, FP model is ideal but the implementation of loss is necessary. To
implement loss during slowing down process, effective confinement time of EP isevaluated, experimentally.

GNET

•
•
•

The database construction of these effective confinement times (Wceff.) is ongoing. Systematic scanof magnetic configuration will provide the confinement database of EPs on magnetic ripples.
The database will be extended to diffusive model (Deff.) of the EP transport with EP driven
instabilities[1], where, we can include the transport without instabilities by ‫ܦ‬௘௙௙ = ܽଶ Τ5.8߬௖ ௘௙௙. .
The experimental results are also used to validate EP transport simulation, like GNET-code.
[1] W.W.Heidbrink et al., Nucl. Fusion 53(2013) 093006

60

PWI studies with long time scale is also important.
Revival of wall pumping was observed at the 48 min. long pulse operation in LHD
R¾

Particle balance in LHD long pulse
discharge is shown in Fig.(c)¾ Particle exhaust by the wall isevaluated by the subtraction of theparticle exhaust by vacuum pumpfrom the particle influx by gas
puffing.
¾ The particle pumping rate can beevaluated from the slope of theexhaust curve.
¾ Particle exhaust by wall:

Particle influx
by Gas puffing

9 Phase 1: ~ 0.2 Pa m3/s
9 Phase 2: ~ -0.01 Pa m3/s
Negative pumping rate !!
䖼 Emitting gas from the wall
9 Phase 3: ~ 0.04 Pa m3/s
䖼 Revival of wall pumping¾ From the analysis on the depositedlayer on the diverter plate. Mixedmaterial layer by carbon and ironseems to play a role on this revival.

Particleexhaustby wall

Particle exhaust by vacuum pump

The LHD steady state operation is suitable platform to explore the long time constant61
behavior in Plasma-Wall Interactions.

Tungsten (W) related PWI studies will be enhanced.

As a material for divertor targets,tangsuten(W) is thought to be thebest candidate.
To enhance the PWI study for future
fusion reactor, a replacement ofdivertor target plate to bulk W
and/or W coated Carbon tile isconsidered. To examine theinfluence of W on LHD operation,
the W-coated Carbon divertor was
installed at one toroidal section
from FY2018.

W coated Carbon divertor

62

PROMOTION OF
COLLABORATION
63

Issues of Evaluation (3)3. Promotion of collaborationඹྠ◊✲䛾᥎㐍(7) Does the LHD project play the role of a global COE in the research with helicaldevices by constructing and using the research network among domestic andinternational universities and research institutes?
ᅜෆእ䛾኱Ꮫ䜔◊✲ᶵ㛵䛸䛾◊✲䝛䝑䝖䝽䞊䜽䛜ᵓ⠏䞉ά⏝䛥䜜䚸䝦䝸䜹䝹ᆺ⿦⨨◊✲䛻䛚䛡䜛ᅜෆእ䛾COE䛸䛧䛶䛾ᙺ๭䜢ᯝ䛯䛧䛶䛔䜛䛛䚹(8) Does the LHD project promote cooperation with and contribute to ITER/BA?
Further, does the LHD project contribute to the research and development ofa reactor? (From the third mid-term plan)64

Domestic collaboration system
Three frameworks of domestic collaboration research are established
General

LHD Project

Bilateral

1,)6

1,)6

1,)6

䠨䠤䠠

Univ.

Univ.

Univ.

Univ.

Univ.

Univ.

Fusion Community

Univ.

Osaka

KyushuToyama

Univ.

Univ.
Univ.

Univ.
Univ.
Univ.

Kyoto

Tsukuba

Univ.

Univ.
Univ.

Fusion Community

Univ.

• Collaboration programs using
experimental device orcomputer in NIFS
• Wide area from basic plasma to
nuclear fusion• Small-scale symposiums orworkshops are supported• 413 topics (2018)

Univ.

Univ.

Univ.

Univ.

Univ.

Univ.

Univ.

Fusion Community• Unique facilities in university
research centers can be used byresearchers across Japan, as if itwere in NIFS.
• Each research center undertakes
the research subjects among
important common issues in the
nuclear fusion research.
• 101 topics (2018)• R&D programs in universities
aiming at future application to
LHD. Three-year program is
accepted although other two
category permit only singleyear program.
• 24 topics (2018)223 universities/institutes, 1524 collaborators (2017)65

Bilateral collaboration research
Fusion Research Community
Since 2010

GAMMA-10㻝㻜㻜㻌㻯㼕㻌㼠㼞㼕㼠㼕㼡㼙㻌㼔㼍㼚㼐㼘㼕㼚㼓㻌㼟㼥㼟㼠㼑㼙PWI study with hydrogen isotope,
tritium process technology

Kyushu Univ.

NIFS

Boundary plasma study, developmentof high power gyrotron

Kyoto
Univ.

㻽㼁㻱㻿㼀

Study of steadystate plasma

Heliotron J
LHD

Optimization of helicalmagnetic configuration㻸㻲㻱㼄㻌㻸㼍㼟㼑㼞

Osaka
Univ.
niv.

Human resource development

Stricter selection of focus

Univ. Tsukuba

Univ.
ToyamaFast ignition study with
LFEX petawatt laser

Enhancement of collaboration

Univ.

66

International Collaboration Researches
Bilateral Coordination
US-Japan
Korea-Japan
China-Japan
Russia-Japan
Australia-Japan
EU-Japan

Activities in 3 Bilateral Coordination withintergovernmental agreements
J/China

J/Korea

J/US

Personnel exchange inFY2017

man

day

man

day

man

day

to NIFS/Japan

7

61

45

163

81

360

from NIFS/Japan

41

258

34

157

71

777

Multilateral Coordination under IEA
Stellartor-Heliotron Concept (chair 2006-2015)
Plasma Wall Interaction
Spherical Tori
(Steady State Operation)

Improve physics base of theStellarator-Heliotron concept
and enhance the effectivenessand productivity of R&D efforts

Coordination with Other Institutes
29 International Academic Exchange Agreements
67

Collaborations with IPP Greifswald (W7-X)
TESPEL for impurity
transport study
now operating

Faraday cup for high energy lostion detection

CXRS for H/D ratio measurement
Scintillating fiber detector forsecondary neutron measurement68Collaborations with U. Wisconsin Madison
High frequency power supply
for high speed Thomson scattering system

Combination with high speed laser enables ~ 10 kHz measurement,
which is useful for- MHD study- transient phenomena (L/H, attach/detach, ELM, etc.) observations
69

Issues of Evaluation (3)3. Promotion of collaboration(7) Does the LHD project play the role of a global COE in the research with helicaldevices by constructing and using the research network among domestic andinternational universities and research institutes?
(8) Does the LHD project promote cooperation with and contribute to ITER/BA?
Further, does the LHD project contribute to the research and development ofa reactor? (From the third mid-term plan)
ITERィ⏬䞉BAάື䛸䛾㐃ᦠ䚸㈉⊩䛜⾜䜟䜜䛶䛔䜛䛛䚹䜎䛯䚸ཎᆺ⅔◊✲㛤Ⓨ䛻ᐤ୚䛧䛶䛔䜛䛛䚹䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

70

Contributions to ITER/BA (1)Contract with JA-DA- Performance examination of the ITERTF coil connection

Contract with ITER-IO- High power tube test for ITER ICH system* 1.4MW/3s, 1.3MW/10s, 1MW/100s at 65
MHz using 4CM2500KG achieved- Negative ion source for NBI- ITER Cryo-plant Process Study* Dynamic simulation for the supercriticalhelium test loop experiment* Full-scale TF structure modelling withsimulation under two base line scenarios, 15& 17 MA, with Plasma disruption followed by
the slow ramp down and the fast discharge

ITER TF joint- Design of the dispersion-interferometer71

Contributions to ITER/BA (2)Contributions to JT-60SA:- performance examination of the JT-60SA EF
and CS coils- development of diagnostics, fueling system- making the JT-60SA Research plan
- management of collaboration

BA collaborations:- DEMO design collaboration- DEMO R&D collaboration- Reduced-activation ferritic steel- SiC/SiC composit- JET ILW PWI research- IFMIF/EVEDA collaboration- management of BA* steering committee member* IFERC project leader

JT-60SA CS coil72

HUMAN RESOURCE DEVELOPMENTAND EFFORTS TOWARD
UNDERSTANDING BY SOCIETY
73

Issues of Evaluation (4)4. Human Resource Development andEfforts toward Understanding by Societyேᮦ⫱ᡂ䚸♫఍䛾⌮ゎ䜈ྥ䛡䛯ྲྀ䜚⤌䜏䠄䠕䠅Does the LHD project contribute to the human resource developmentof researchers who are active internationally and lead the domestic
and international fusion research?
ᅜෆእ䛾᰾⼥ྜ◊✲䜢≌ᘬ䛧䚸ᅜ㝿ⓗ䛻䜒ά㌍䛩䜛ேᮦ䛾⫱ᡂ䛻㈉⊩䛧䛶䛔䜛䛛䚹䠄䠍䠌䠅Does the LHD project cooperate with local governments and engage
in deepening the understanding of the deuterium experiments by
local residents?

74

Development of human resources throughinternational collaborations
Developing human resources for fusion science is essential to keep andenhance the research potential for next generation
In order to perform it, NIFS has- contributed to the education for graduate
students via SOKENDAI (the graduate
university for advanced studies)- accepted graduate students and internshipstudents from domestic and overseas
universities and institutes- has dispatched graduate students and young
researchers to overseas institutes which havethe academic exchange agreements
Graduate students in NIFS
- SOKENDAI: 15, including 6 from abroad (2018)- Other universities: 38 (2017)75

Active Scientists raised locally, blooming globally

Prof. Y. Xu,
Southwest Jiaotong Univ.
JSPS fellow in NIFS

Dr. P. Drewelow
IPP Greifswald, Scientist,
Ph.D. thesis in LHD exp.

Prof. Y. Liang,
FZJ/HHU,Huazhong Univ.,
SOKENDAICollaboration
education

NIFS

SOKENDAI

Assoc. Prof. S. Geng,
SWIP,
SOKENDAIDr. S. Du,
General Atomics,
SOKENDAI76

Issues of Evaluation (4)4. Human Resource Development and Efforts toward
Understanding by Society(9) Does the LHD project contribute to the human resource developmentof researchers who are active internationally and lead the domestic
and international fusion research?
(10) Does the LHD project cooperate with local governments, and engage
in deepening the understanding of the deuterium experiments by
local residents?
⮬἞య䛸䛾㐃ᦠ䜢ᅗ䜛䛸䛸䜒䛻䚸㔜Ỉ⣲ᐇ㦂䛻ᑐ䛩䜛ᆅᇦఫẸ䛾⌮ゎ䜢῝䜑䜛ྲྀ⤌䜏䜢⾜䛳䛶䛔䜛䛛䚹

77

Public release of information (1)NIFS Tour- Throughout the year, NIFS welcomes visitors
for the facility tour.
- Visitors can see several experimental facilities
and hear a summary of NIFS research activities.
- Tour is on weekday and takes about 90 minutes.
- Three staffed specializing in NIFS tour.
Open Campus- Once a year in autumn, since 1998
- 1500 visitors in 2018
Fusionn Festaa in Tokyo- Once a year in Tokyo as science
event along the lines of Open
Campus, since 2010
- Open lectures and experiencebased event like scientifichandcraft- 2650 visitors in 201878

school
student# student

Educational contributions- Educational partnership activities of Super
Science High School (SSH) :25 high schools, 842 students (2017).
- Visiting lectures: 8 high schools (2017)- Internship programs for junior-high school, highschool and technical college students:
18 schools, 33 students (2017)# high school

Public release of information (2)year
Public Forum- Explanation about LHD and deuterium experiment
to increase local citizen’s recognition of NIFS’s
scientific achievements- Forums take place at community centers at Toki,
Tajimi, and Mizunami, since 2006
- In FY 2018, 235 citizens joined the Forum- Total: 5,365 (for 13 years)
79

Public release of information (3)Publications- Design and publication of the PR magazines and leaflets:“Plasma-kun Dayori” (every 2 months)“NIFS NEWS” (every 2 months)“Fusion – Energy to Pave the Way for Future”,“NIFS Do Research Aimed at Extracting Energy from
Sea Water”,“Introduction to NIFS and the NIFS Tour”,
and “Welcome to NIFS”
Autonom

Web- Introductions to fusion- about NIFS
- about LHD- about deuterium experiment- Safety80

Cooperation with Local Autonomies
Cooperationn withh local commission- In 2013, NIFS concluded the agreement for
D-D experiment with local autonomies- Following the agreement, Gifu pref., Toki,
Tajimi and Mizunami city established the
Safety Surveillance Commission for National
Institute for Fusion Science- NIFS informs safety report and experimental
schedule and status regularly to thecommission.
Collaboration Research with “Toki Cityy Plasma Research Committee”- In 1979, collaboration research started
with Toki City Plasma ResearchCommittee started, which consists ofhigh and junior high school teachers- Main activities are䞉 holding lecture meetings on energy
and environmental issues
䞉 measurement of environmental radioactivities at 18 locations in Tono area81References

Table of Evaluation Results for the 2018 External Peer Review

Table of Evaluation Results for the 2018 External Peer Review"Large Helical Device Project"
Ⅰ. Points for Evaluation（１）Is the implementation system built to achieve deuterium experiments with coordinating domestic and international
researchers? (From the third mid-term plan)（２）Are preparations of safety management equipment and of facilities and their countermeasures performed appropriately forstarting the deuterium experiments? Was the safety management system built as planned? (From the third mid-term plan)（３）Does the LHD project obtain high-performance plasma by the deuterium experiments and produce excellent researchachievements with high academic value? (From the third mid-term plan)（４）Does the LHD project obtain prospects for development of academic research toward a comprehensive understanding of
toroidal plasmas? (From the third mid-term plan)（５）Is preparation of necessary devices and facilities for the main device, heating systems, diagnostics, and others advanced
appropriately according to the research plan of the deuterium experiments?
（６）Will the LHD project consider further research development towards the realization of a fusion reactor based on theachievements of the LHD project?
（７）Does the LHD project play the role of a global COE in the research with helical devices by constructing and using the research
network among domestic and international universities and research institutes?
（８）Does the LHD project promote cooperation with and contribute to ITER/BA? Further, does the LHD project contribute to theresearch and development of the DEMO reactor? (From the third mid-term plan)（９）Does the LHD project contribute to the human resource development of researchers who are active internationally and leadthe domestic and international fusion research?
（10）Does the LHD project cooperate with local governments and engage in deepening the understanding of the deuterium
experiments by local residents? Does the project also contribute to achieving a broad social understanding of fusion research?

Ⅱ. Tabele of Evaluation
Point of Evaluation

Score

５
(Extremely highly commmendable)

４(Highly commendable)

３(Commendable)

２(Adequate)１(Inadequate)

Average Score

Number of persons

（１）

（２）

（３）

（４）

（５）

（６）

（７）

（８）

（９）

（１０）

10

12

9

5

9

1

3

4

4

10

5

3

5

11

4

8

12

7

9

6

1

1

2

0

3

7

1

5

3

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

4.56

4.69

4.44

4.31

4.38

3.63

4.13

3.94

4.06

4.63

Average Score※The evaluation result is a combination of the results of domestic committee members (12 persons)and foreign committee members (4 persons).

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
0.75
0.50
0.25
0.00

4.56

4.69

4.44

4.31

4.63

4.38

4.13
3.63

(1)

(2)

(3)

(4)

(5)

(6)

Point of Evaluation

(7)

3.94

4.06

(8)

(9)

(10)

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/