National Institutes of Natural Sciences

National Institute for Fusion Science

Peer Review Reports for FY2017

March, 2018
National Institute for Fusion Science
Advisory Committee External Peer Review Committee㻯㼛㼚㼠㼑㼚㼠㼟㻌㻌㻌㻯㼔㼍㼜㼠㼑㼞㻌 㻝㻌 㻮㼍㼏㼗㼓㼞㼛㼡㼚㼐㻌㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㻌㻝㻌㻌㻌㻯㼔㼍㼜㼠㼑㼞㻌 㻞㻌 㻿㼡㼙㼙㼍㼞㼥㻌㼛㼒㻌㻱㼢㼍㼘㼡㼍㼠㼕㼛㼚㼟㻘㻌㼍㼚㼐㻌㻼㼞㼛㼜㼛㼟㼍㼘㼟㻌㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㻌㻡㻌㻝㻚㻌㻿㼡㼙㼙㼍㼞㼥㻌㼛㼒㻌㻱㼢㼍㼘㼡㼍㼠㼕㼛㼚㻌㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㻌㻡㻌㻞㻚㻌㻼㼞㼛㼜㼛㼟㼍㼘㼟㻌㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㻌㻝㻞㻌㻌㻌㻯㼔㼍㼜㼠㼑㼞㻌 㻟㻌 㻵㼚㻌㻯㼘㼛㼟㼕㼚㼓㻌㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㽂㻌㻝㻟㻌㻌㻌㻌㻰㼛㼏㼡㼙㼑㼚㼠㼟㻌 㻌 㻌㻝㻚㻌㻞㻜㻝㻣㻌㻱㼤㼠㼑㼞㼚㼍㼘㻌㻼㼑㼑㼞㻌㻾㼑㼢㼕㼑㼣㻌㻼㼞㼑㼟㼑㼚㼠㼍㼠㼕㼛㼚㻌㻹㼍㼠㼑㼞㼕㼍㼘㼟㻌㻌㻌㻾㼑㼒㼑㼞㼑㼚㼏㼑㼟㻌㻝㻚㻌㼀㼍㼎㼘㼑㻌㼛㼒㻌㻱㼢㼍㼘㼡㼍㼠㼕㼛㼚㻌㻾㼑㼟㼡㼘㼠㼟㻌㼒㼛㼞㻌㼠㼔㼑㻌㻞㻜㻝㻣㻌㻱㼤㼠㼑㼞㼚㼍㼘㻌㻼㼑㼑㼞㻌㻾㼑㼢㼕㼑㼣㻌 㻌䇾㻲㼡㼟㼕㼛㼚㻌㻱㼚㼓㼕㼚㼑㼑㼞㼕㼚㼓㻌㻾㼑㼟㼑㼍㼞㼏㼔㻌㻼㼞㼛㼖㼑㼏㼠䇿㻌㻌Chapter 1 Background
The National Institute for Fusion Science (below as NIFS) was established in 1989 as
an inter-university research institute, and utilizes the Large Helical Device (below as
LHD) as the principal device to advance fusion research in universities in Japan.
The LHD, which was planned by bearing the support and the expectations of thefusion community, has the special characteristic of producing the heliotron-type magnetic
field, which is an idea unique to Japan. In addition to generating high-performancehelical-type plasma through high-power heating, NIFS is advancing with experimental
research that aims to clarify physical and technological issues for realizing the magnetic
field confinement fusion reactor. On the other hand, parallel with this, in analyses offusion plasmas having fundamental complexities, theoretical research that uses largescale simulations is essential. For that reason, a supercomputer for exclusive use wasintroduced at NIFS. We are advancing with leading-edge research by making thissupercomputer at NIFS available for use to fusion theory researchers in Japan throughcollaborative research. Moreover, since 2010, in order to further strengthen the centripetal
power of NIFS as a Center of Excellence (below as COE) in the field of plasma fusion
research we have organized three research projects, these being LHD, theory andsimulation, and reactor engineering.
Further, looking toward achieving the fusion reactor, we have initiated research
project that 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 respond resourcefully
to new topics.
In this period, there have been changes to the structure of the domestic academic
research system. Since 2004, NIFS has been a research institute under the Inter-University
Research Institute Corporation National Institutes of Natural Sciences (below as NINS).
Upon becoming an inter-university research institute corporation, a system for mid-termgoals 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 upon administrative management. However, at NIFS it has been determinedthat receiving external evaluations of research results is important. Under the NIFS
Advisory Committee, each year an External Peer Review Committee is organized and themembers evaluate the research. The topics of evaluation are determined by the Advisory-1-

Committee. The evaluation is undertaken by the members of 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, 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 anddecided upon by the Advisory Committee, and those topics for evaluation differ each year.
Most recently, in 2014 the Deuterium Experiment Implementation Planning, in 2015 theNumerical Simulation Reactor Research Project, and in 2016 Collaborative Researchwere topics evaluated by external reviewers. This year, 2017, the “Fusion Engineering
Research 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, here were three experts from outside NIFS and one expert from abroad. Thus was
the External Peer Review Committee composed, and thereby the evaluation wasundertaken
The first meeting of the External Peer Review Committee including the Experts’Committee was convened on October 20, 2017. The Committee discussed the process formoving forward with this fiscal year’s external peer review, and decided upon theperspective of the evaluation. On December 2, 2017, the second meeting of the ExternalPeer Review Committee and the Experts’ Committee was held. From NIFS was provided
a detailed explanation that utilized documents from the material of viewgraphs andreports based on the perspectives (see the documents section). A question-and-answer
section also was held. Subsequently, the third meeting of the External Peer Review
Committee and the Experts’ Committee was held on February 2, 2018. Together withholding another question and answer session with NIFS, evaluation work based on the
topics of the evaluation and the coordination of the evaluation work were undertaken. We
compiled the external peer review report (draft) based upon the discussion to this pointand further discussions were held by electronic mail. Upon confirmation and examinationby the External Peer Review Committee and the Experts’ Committee, we compiled thefinal report. Please see Reference Material 4 for the meeting schedule of the External Peer
Review Committee and the Experts’ Committee.
Moreover, the perspectives for the evaluation of “Fusion Engineering Research
Project,” which is the title of this year’s topic, are considered indispensable in the-2-evaluation of the “Fusion Engineering Research 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, based upon the proposal that was implemented in the External Peer Review
Report of “Fusion Engineering Research Project” in 2013, we have consulted thefollowing points in the evaluation.
1. In fulfilling the role as a Center of Excellence (COE) in basic technology
development in the field of fusion engineering, is there a deepening of the academic
systemization of leading-edge technologies developed there as engineering?
2. Aiming at developing young researchers who will lead the world, is NIFS
constructing frameworks that will extend human resources and realize improvement
in quality with universities and research institutes?
3. Is NIFS advancing effective management by the introduction of large-scaleequipment and test facilities, the maintenance of the research environment based
upon the arrangement of staff and increase in staff, and the construction ofmaintenance and management systems?
4. Is NIFS contributing to the construction of fusion specifications and standards by
integrating and making databases of results and knowledge?
The perspectives for the “Fusion Engineering Research Project” evaluation are as
below.
1. Design Study on the Helical Fusion Reactor(1) Whether or not the Fusion Engineering Research Project (below as FERP) has shown
continued progress on upgrading and refinement of the helical reactor design study(From the second mid-term plan)(2) Whether or not the FERP has summarized the conceptual design study of the helicalfusion reactor and embodied the numerical targets for each development issue (Fromthe third mid-term plan)(3) Whether or not the design study of the helical fusion reactor and the R&D activitiesof the major components are closely related to each other (From the third mid-termplan)
2. R&D Study on the Fusion Technology Basis-3-

(1) Whether or not the FERP has served as a COE dedicated for the fusion technology
development (From the second mid-term plan)(2) Whether or not the FERP is enhancing interdisciplinary researches to strengthen thebasis of the fusion engineering study (From the second mid-term plan)(3) Whether or not the FERP is improving the facilities for the fusion engineering study
and enhancing the joint-use and collaboration (From the second and third mid-termplans)(4) Whether or not the FERP is enhancing the collaboration research by utilizing theframeworks of “Bilateral Collaboration Research” and “LHD Project Collaboration
Research” (From the second mid-term plan)(5) Whether or not the FERP has served as a COE to contribute to the international
activities including ITER and BA, jointly with universities (From the second midterm plan)(6) Whether or not the FERP is providing distinctive education in the field of fusion
engineering research, taking advantage of the function as an inter-university research
institute (From the second mid-term plan)(7) Whether or not the FERP has been closely cooperating with foreign institutions byenhancing researcher exchange and collaboration based on the international
agreements (From the second mid-term plan)(8) Whether or not FERP has contributed to creating research results from universities(From the third mid-term plan)-4-

Chapter 2 Summary of the Evaluation, and Proposals
Based upon the opinions and the discussions at the meetings of the External Peer
Review Committee and Experts’ Committee, we summarize the important points of theevaluation, and we report in writing the proposal regarding promotion of the Fusion
Engineering Research Project.
[1] Summary of the Evaluation
1. Design Study on the Helical Fusion Reactor(1) Whether or not the FERP has shown continued progress on upgrading andrefinement of the helical reactor design study
Maintenance and cost evaluations, as well as analyses that employed simulations,have been continuously undertaken. Not only are improvements and refinement of thehelical-type fusion reactor design being planned, so too are settings of challenging issues
being undertaken, and these are highly evaluated. Further, that reactor designs areconsolidated to a couple of designs by presenting fundamental structural conditions andusage conditions can be evaluated.
On the other hand, regarding the method of separating Basic and Challenging, someappreciation may be anticipated. However, it is necessary to clarify the full image throughconsideration of feasibility and priority. Clearly expressing the engineering feasibility of
the fundamental designs based on the academic and engineering knowledge that has beenachieved to date, further it is sought to identify challenging issues. Moreover, it will benecessary from now to identify differences in the consideration level, overlapping issues
with, and different issues from DEMO reactor designs that are being advanced throughcurrent tokamak devices.
(2) Whether or not the FERP has summarized the conceptual design study of thehelical fusion reactor and embodied the numerical targets for each development
issue
That the development goals for each component are being quantified to the extent
possible is useful for grasping conditions in the advancement of research, and is highly
evaluated.
-5-

On the other hand, the meaning of the numerical goals, the degree of importance of
this topic, the complementary relevance across research topics, the prioritization, and thecharacterization are not clear. From now, strategic endeavors are anticipated. Linked toconceptual designs, the refinement of each topic should be considered further. And forthe above reason, it is necessary that there be a revision of the understanding of Basic andChallenging and of numerical goals. In addition, it is anticipated that there will be aclarification of the approach to “As an overall design, how will optimal integration beachieved?” Regarding the degree of the possibility of achieving the numerical goal andthe overall balance, a semi-quantitative evaluation also is believed to be necessary.
(3) Whether or not the design study of the helical fusion reactor and the R&D
activities of the major components are closely related to each otherCentered on the development of the high-temperature superconductor coils, theblanket, and divertor, well-balanced interlocking between design and developmental
research is highly evaluated. Further, the topics of development research issues related toambitious designs, too, are being treated. That results are visible can be evaluated.
On the other hand, in the helical fusion reactor design, not only Challenging issues,
but also issues to be developed that have high commonalities with the tokamak and should
be breakthrough topics being strongly linked to the Action Plan remain. For that reason,
paying attention to research development in Basic topics it is important to indicate thestrategy in which importance of research development including numerical goals should
be clarified and the competitiveness of priorities in the development research should beindicated. Further, it also is important to indicate the relationship between the goals
expressed by the reactor design and R&D items, and to express feedback to the reactor
design. Further, it is necessary to raise the strategic roadmap which includes thedevelopment of devices and “the time schedule.”
2. R&D Study on the Fusion Technology Basis(1) Whether or not the FERP has served as a COE dedicated for the fusion
technology development
Research concerning important fundamental technologies in the fusion engineering
field is being conducted organically in effective collaborative relationships with
universities, and NIFS, as a COE focused on this field, is satisfactorily fulfilling its roles.
-6-

Further, that NIFS is utilizing hardware actively as a common resource of the fusion
community can be evaluated extremely highly. Further, as a hub for exchanging
information with domestic and international research organizations by reporting domestic
and international meeting results and by hosting IAEA meetings, NIFS is accumulating a
superlative result.
On the other hand, in addition to technology related to the helical reactor, we
anticipate NIFS’ roles as a basic technology development COE in broad aspects of fusion
engineering including other reactor types, being based upon the action plan issued by the
MEXT.Also, it is hoped that there will be appeals for advancement by indicating overall
development strategies for each of the principal engineering technology fields or for eachof the instruments to be developed. Moreover, we also wish NIFS to examine numerical
data regarding how each instrument is utilized and how many academic articles are
published by each researcher that include open journals.
(2) Whether or not the FERP is enhancing interdisciplinary researches to strengthen
the basis of the fusion engineering study
Expanding research horizontally in the interdisciplinary field, and achieving
important results, NIFS is highly evaluated. Further, providing the superlative facilities
and equipment that have been obtained and prepared as an inter-university research
institute as platforms for broad-ranging engineering research, and promoting
development of collaborative research with companies under the idea of “revolutionary
energy circulation engineering,” NIFS can be evaluated.
On the other hand, from the point of view of the expansion of research ininterdisciplinary fields, there are limits. In the future, we hope that NIFS aims at
generalizing toward the engineering basis founded upon technical advances and making
contribution to academic systemization at the research level that will lead other fields.
Further, in order to advance further in research expansion in interdisciplinary fields, inthe future, we anticipate endeavors that will utilize the delivery of information towardoutside research fields and that utilize the URA system. Further, regarding how
interdisciplinary research is conducted, as it does not necessarily move in a direction ofacademic creation, it may be thought beneficial to examine approaches for pioneeringtransdisciplinary fields based upon the requests of society.
(3) Whether or not the FERP is improving the facilities for the fusion engineering
study and enhancing the joint-use and collaboration-7-

As preparation and expansion of the engineering experiment equipment, we canhighly evaluate that the introduction of transmission electron microscope, of the highheat flux electron beam irradiation experimental device ACT 2, and of the superconductor
coil experimental devices is being affixed to the NIFS experimental device, and these arebeing utilized for joint use and collaborative research, and that research results are
steadily being achieved. One example of this at NIFS is the JT-60SA superconductor
center solenoid coils experiment.
On the other hand, so as to not increase the burden upon NIFS researchers, and to
improve further the convenience to researchers through maintenance and management ofsuch equipment, it is essential to ensure the technical staff who manage the equipment.
Further, in the future, if there are plans for the enhancement of related machinery andlong-term management of machinery, upon setting goals and targets it is hoped that there
will be examination of the machinery plan including the appointment of staff. For thatreason, discussion based upon each machine’s usage conditions and data regarding
research results will be expected. Together, as the core of the next engineering device
development which aims towards the future fusion reactor, in order for more effective
management of collaborative use and collaborative research by use of leading-edge
equipment, further information disseminated to the research community is anticipated.
(4) Whether or not the FERP is enhancing the collaboration research by utilizing theframeworks of “Bilateral Collaboration Research” and “LHD Project
Collaboration Research”
Through bilateral collaboration research, with links to Toyama University, Universityof Tsukuba, Kyushu University, and other universities, the collaborative research baseregarding reactor research has been expanded. With links to generating results, we canhighly evaluate the contributions that will surely strengthen the functions of universities
such as utilization of distinctive equipment and facility at research institution of core
universities. Further, regarding LHD Project Collaboration Research, the temperatureelevated desorption spectrum diagnostic device, plasma irradiation device development,
advanced materials testing research, evaluation of tritium’s effects upon the living human
body, blanket, divertor, and other topics in fusion engineering are implemented ascollaborative research, and results are emerging. Together with Bilateral Collaboration
Research and LHD Project Collaboration Research, through promotion of linkages withlaboratories at universities for the reactor engineering field endeavoring to expand-8-

collaborative research is highly evaluated. From now, further expansion of BilateralCollaboration Research such as the re-introduction of university-affiliated research
centers that is to become the research basis is expected. The established policy forcollaborative research themes that reflects the characteristics of the fusion reactor
research project and of each center, and how the research results evolve from thecollaborative research system, too, should be considered.
(5) Whether or not the FERP has served as a COE to contribute to the international
activities including ITER and BA, jointly with universities
As contributions to international projects under the coordination and cooperation
system with universities, the projects such as the superconductor coil test experiments
conducted on ITER and on JT-60SA, the collaborative research on ITER for the lowtemperature systems and the neutral particle injection device, the BA activities on JT60SA, the DEMO development research at IFERC, the collaborative research on IFMIFEVEDA, heating device development, enhancement of database on plasma-facing
materials and atoms and molecules, are numerous, and this is highly evaluated. Further,in deciding the action plan regarding DEMO reactor design by the joint-core team,
implementing important contributions under cooperation with universities byparticipating as a COE for this field is highly evaluated.
Further, the contribution to the ITER and BA activities is a matter of course, and incomposing the action plan aiming toward the tokamak DEMO reactor NIFS is anticipatedto show the strategy, that is, in what direction is fusion research at universities in Japan
being guided, from a higher perspective as a COE including also NIFS’ organizational
contributions.
(6) Whether or not the FERP is providing distinctive education in the field of fusion
engineering research, taking advantage of the function as an inter-university
research instituteUtilizing NIFS’ facilities for fusion research under collaborative use and collaborative
research with universities, we can highly evaluate that excellent educational opportunities
are being provided at universities for the purpose of advancing education and real-world
education, and these results are linked to numerous academic papers and theses ofgraduate students, leading to producing results. Further, at Sokendai (The Graduate
University for Advanced Studies), NIFS is advancing with the development of doctoral-9-

course graduate students, and through enrolling graduate students entrusted fromuniversities as an inter-university research institute, enhancing coordinated graduate
schools and summer school programs, NIFS contributes to the distinctive education in
the plasma and fusion fields.
On the other hand, the number of doctoral degrees issued is not many. Further, itcannot be said that a unique education in the field of fusion reactor engineering is being
undertaken in an organized style. In the future, together with links to universities andother facilities, we anticipate a leading role that NIFS can do precisely to be fulfilled. For
that reason, it is necessary to advance our efforts in the participation of students inresearch utilizing leading-edge devices, in relationships and linkages between Sokendai
and other universities, and in securing excellent human resources.
(7) Whether or not the FERP has been closely cooperating with foreign institutions
by enhancing researcher exchange and collaboration based on the international
agreements
Based upon international cooperation agreements, the Japan-United States
cooperative program projects such as TITAN and PHENIX, and Japan-China and JapanRepublic of Korea programs such as the Post-CUP and the A3 Foresight programs havebeen implemented. Further, functioning as a core institute for collaborative research under
the international coordination such as the IEA-sponsored stellarator/heliotron agreement
and the PWI agreement, and the research projects and workshops coordinated by IAEA,
NIFS is advancing close collaborative research linkages with overseas researchers. Thisis highly evaluated. Further, NIFS is fulfilling functions as a COE that manages andimplements international collaborative research. In the future, we anticipate consideration
on future programs, the clarification of these programs being all-Japan programs, and thefurther progress of international collaborative research.
(8) Whether or not FERP has contributed to creating research results fromuniversities
Through Bilateral Collaboration Research, LHD Project Collaboration Research,
General Collaboration Research, collaborative use of fusion reactor engineering
equipment, and cooperative research activities with foreign countries such as the JapanUS cooperation program, numerous articles by university researchers have been
published. And international articles and awards have been published and received,- 10 -

respectively, on plasma engineering and fusion reactor engineering research. Further,
research funding related to this research is not only contributing significantly to theresearch results from universities but also to education. These are highly evaluated.
On the other hand, even after the enhancement of the engineering experimental
equipment, the number of related research articles changed little. Further, there is concernthat the number of doctoral degrees at universities is fewer. In addition, because thecontributions towards strengthening the functions of universities from an inter-university
research institute will become all the more significant, it will be necessary to continuously
and systematically collect high-quality verifiable data objectively regarding this issue. At
that time, not only factual data, we anticipate that the strategy and standing as the interuniversity research institute will be clarified further.

- 11 -

[2] Proposals
In the current evaluation, we discussed the Fusion Engineering Research Project at
NIFS. Based upon the contents of that discussion, below we offer our proposal regarding
the future direction of the Fusion Engineering Research Project.
(1) Regarding the improvement and the refinement of the helical-type fusion reactor
design, we anticipate clarification of the full image that will consider the realizationand the priority of the methods, and also clarification of the comparison with the
DEMO reactor design of the tokamak-type being forwarded.
(2) While strongly linking the conceptual design and the developmental research for thecore devices and instruments, the meaning of the numerical goals, the significance ofthe topics, the complementary relationships among topics, and the degree of priority
and standing should be clarified and a still more strategic effort is anticipated.
(3) In the enhancement and expansion of the fusion reactor engineering experimental
equipment, for developing the Fusion Engineering Research Project and thecollaborative research, as well as for increasing accessibility to users including
graduate students, the enhancement plans that include staffing as well as the goals
should be made concrete.
(4) We anticipate the construction of an education system that leads to graduate educationand creation of career paths based upon cross-cutting and interdisciplinary links touniversities and research institutes, for aiming at nurturing human resources for a
future in fusion reactor development research in addition to assisting continuouslywith producing research results from universities, through collaborative use andcollaborative research beginning with Bilateral Collaboration Research and LHD
Project Collaboration Research.
(5) We anticipate that displaying views of the direction and the strategy from a higher
perspective regarding fusion research in Japanese universities as an inter-university
research institute, NIFS plays the role of a COE for basic technology development in
the entire field of fusion engineering including other types such as ITER and BA
activities, the Action Plan of MEXT that aims toward the DEMO reactor.

- 12 -

Chapter 3 In ClosingIn order to strengthen further the centripetal force of the COE in the Plasma-Nuclear
Fusion field, at NIFS from 2010 (Heisei 22), we constructed the three projects of LHD,
theory and simulation, and fusion engineering aiming at realizing the fusion reactor, wehave initiated research planning by unifying these 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 free will. Due to this, we anticipate the promotion of links with LHD, theory
and simulation, and fusion engineering, and we anticipate being able to respondresourcefully to new topics.
In the NIFS External Peer Review Committee review, in 2014 (Heisei 26) the
implementation of the LHD deuterium experiment, in 2015 (Heisei 27) the Numerical
Simulation Reactor Research Project, and in 2016 (Heisei 28) the Collaborative Research,were evaluated. Thus, in this current year of 2018 (Heisei 30) the Advisory Committee
undertook an external evaluation that focused on “The Fusion Engineering Research
Project.” The External Peer Review Committee was composed of ten members of theAdvisory Committee outside of NIFS and three members from abroad, further, threemembers outside of NIFS, and one member from abroad as the Experts’ Committee. The
points below were evaluated.
1. Design Study on the Helical Fusion Reactor(1) Whether or not the FERP has shown continued progress on upgrading and refinementof the helical reactor design study (From the second mid-term plan)(2) Whether or not the FERP has summarized the conceptual design study of the helicalfusion reactor and embodied the numerical targets for each development issue (Fromthe third mid-term plan)(3) Whether or not the design study of the helical fusion reactor and the R&D activitiesof the major components are closely related to each other (From the third mid-termplan)
2. R&D Study on the Fusion Technology Basis(1) Whether or not the FERP has served as a COE dedicated for the fusion technology
development (From the second mid-term plan)(2) Whether or not the FERP is enhancing interdisciplinary researches to strengthen thebasis of the fusion engineering study (From the second mid-term plan)- 13 -

(3) Whether or not the FERP is improving the facilities for the fusion engineering study
and enhancing the joint-use and collaboration (From the second and third mid-termplans)(4) Whether or not the FERP is enhancing the collaboration research by utilizing theframeworks of “Bilateral Collaboration Research” and “LHD Project Collaboration
Research” (From the second mid-term plan)(5) Whether or not the FERP has served as a COE to contribute to the international
activities including ITER and BA, jointly with universities (From the second midterm plan)(6) Whether or not the FERP is providing distinctive education in the field of fusion
engineering research, taking advantage of the function as an inter-university research
institute (From the second mid-term plan)(7) Whether or not the FERP has been closely cooperating with foreign institutions byenhancing researcher exchange and collaboration based on the international
agreements (From the second mid-term plan)(8) Whether or not FERP has contributed to creating research results from universities(From the third mid-term plan)
The External Peer Review Committee was convened four times from October 2017
through February 2018 including e-mail discussion committee. Detailed explanations of
the evaluation topics provided from NIFS and active discussions were held. The ExternalPeer Review Committee members summarize evaluation results and submit this report.
As the result of the external evaluation of the “Fusion Engineering Research Project,”in general, a recommendation of a high evaluation was received. Further, regarding theevaluation points above, the points of playing the role of COE in basic technology
development in the fusion engineering field, the points of advancing and expanding
cooperative research through utilizing effectively the system of Bilateral Collaboration
Research, LHD Project Collaboration Research, and the points of advancing cooperation
through collaborative research and exchange of researchers with overseas research bases,
are highly evaluated, and in the future, still further development is anticipated. Regarding
sophistication and refinement of the helical-type fusion reactor design and fundamental
research on fusion engineering, in general these are evaluated highly. However, regarding
targeting the numerical goals of development topics, and the interlocking between reactor
design research and fusion engineering basic research, additional efforts are required.
Further, organic linkages are anticipated regarding the ITER and BA activities, and the- 14 -

Action Plan of MEXT toward the DEMO reactor. The strengthening of linkages with
developmental research beginning with ITER may be greatly anticipated to contributetoward academic systemization of the base of fusion engineering and expanding the broad
areas of engineering fields. On the other hand, high-level collaborative use andcollaborative research which utilized engineering experiment equipment expanded
broadly in Heisei 24 (2012) was promoted. The strengthening of the hardware can behighly evaluated. However, regarding the software such as generalization andsystemization of technological developments based upon the hardware toward
interdisciplinary engineering research utilization for high-level specialized education, andfurther aiming at creating research results coordinated with universities, further activationis required in the future. However, for promoting this type of research and education it is
crucial that not only NIFS but also the fusion engineering community including
universities should advance as an integrated manner.
In conclusion, the proposal for future advancement of the NIFS Fusion Engineering
Research Project is provided below.
(1) Regarding the improvement and the refinement of the helical-type fusion reactor
design, we anticipate clarification of the full image that will consider the realizationand the priority of the methods, and also clarification of the comparison with the
DEMO reactor design of the tokamak-type being forwarded.
(2) While strongly linking the conceptual design and the developmental research for thecore devices and instruments, the meaning of the numerical goals, the significance ofthe topics, the complementary relationships among topics, and the degree of priority
and standing should be clarified and a still more strategic effort is anticipated.
(3) In the enhancement and expansion of the fusion reactor engineering experimental
equipment, for developing the Fusion Engineering Research Project and thecollaborative research, as well as for increasing accessibility to users including
graduate students, the enhancement plans that include staffing as well as the goals
should be made concrete.
(4) We anticipate the construction of an education system that leads to graduate educationand creation of career paths based upon cross-cutting and interdisciplinary links touniversities and research institutes, for aiming at nurturing human resources for a- 15 -

future in fusion reactor development research in addition to assisting continuouslywith producing research results from universities, through collaborative use andcollaborative research beginning with Bilateral Collaboration Research and LHD
Project Collaboration Research.
(5) We anticipate that displaying views of the direction and the strategy from a higher
perspective regarding fusion research in Japanese universities as an inter-university
research institute, NIFS plays the role of a COE for basic technology development in
the entire field of fusion reactor engineering including other types such as ITER and
BA activities, the Action Plan of MEXT that aims toward the DEMO reactor.

- 16 -㻌㻌㻌㻰㼛㼏㼡㼙㼑㼚㼠㼟㻌 㻌㻌㻌㻝㻚㻌㻞㻜㻝㻣㻌㻱㼤㼠㼑㼞㼚㼍㼘㻌㻼㼑㼑㼞㻌㻾㼑㼢㼕㼑㼣㻌㻼㼞㼑㼟㼑㼚㼠㼍㼠㼕㼛㼚㻌㻹㼍㼠㼑㼞㼕㼍㼘㼟㻌





















2017 NIFS External Review (Nagoya, Dec. 2, 2017)

Prof. Takeo MUROGA
Executive Director of FERP (on Science)Prof. Nagato YANAGI
Executive Director of FERP (on Device)
National Institute for Fusion ScienceEvaluation Points for FERPThe External Peer Review Committee presented
three evaluation points for1. Design Study on the Helical Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲

and eight evaluation points for

2. R&D Study on the Fusion Technology BasisᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲according to the 2nd and 3rd mid-term plans of NIFS,
and

Suggestions from the last external review(2013)are considered as a reference for the evaluation1. Design Study on the
Helical Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲(1) Whether or not the FERP has shown continued
progress on upgrading and refinement of the helical
reactor design study (from the 2nd mid-term plan)䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛾㧗ᗘ໬䞉⢭ᐦ໬䜢⥅⥆ⓗ䛻㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(2) Whether or not the FERP has summarized theconceptual design of the helical fusion reactor and has
embodied the numerical targets for each development
issue (from the 3rd mid-term plan)䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾ᴫᛕタィ䜢䜎䛸䜑䚸ྛ㛤Ⓨㄢ㢟䛾ᩘ್┠ᶆ䜢ලయ໬䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(3) Whether or not the helical fusion reactor design study
and the R&D activities on major components areclosely related with each other (from the 3rd mid-term plan)䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛸ᇶᖿᶵჾ䛾㛤Ⓨ◊✲䛸䛜㐃ື䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

2. R&D Study to Develop the
Fusion Technology BasesᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(1) Whether or not the FERP has served as a COE
dedicated for fusion technology development
᰾⼥ྜᕤᏛศ㔝䛻䛚䛡䜛ᇶ┙ᢏ⾡㛤Ⓨ䛾COE䛸䛧䛶䛾ᙺ๭䜢ᯝ䛯䛧䛶䛔䜛䛛(2) Whether or not the FERP is enhancing interdisciplinary
researches to strengthen the basis of the fusion
engineering study (from the 2nd mid-term plan)ᕤᏛ◊✲䛾ᇶ♏䛸䛺䜛Ꮫ㝿㡿ᇦ䛾◊✲ᣑ඘䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(3) Whether or not the FERP is improving the facilities forthe engineering study and enhancing the joint-use andcollaboration (from the 2nd and 3rd mid-term plans)ᕤᏛᐇ㦂タഛ䛾᭦䛺䜛ᣑ඘䛸㧗ᗘ䛺ඹྠ฼⏝䞉ඹྠ◊✲䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ䚸➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(4) Whether or not the FERP is enhancing thecollaboration research by utilizing the frameworks of“Bilateral Collaboration Research” and “LHD Project
Collaboration Research” (from the 2nd mid-term plan)཮᪉ྥᆺඹྠ◊✲䚸LHDィ⏬ඹྠ◊✲䛺䛹䛾ไᗘ䜢᭷ຠ䛻฼⏝䛧ඹྠ◊✲䛾ᣑ඘䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ
⏬䜘䜚䠅


2. R&D Study to Develop the
Fusion Technology Bases (contd.)ᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(5) Whether or not the FERP has served as a COE to contribute to
the international activities including ITER and BA, jointly with
universities (from the 2nd mid-term plan)ᅜ㝿⇕᰾⼥ྜᐇ㦂⅔ཬ䜃䛂ᖜᗈ䛔䜰䝥䝻䞊䝏䛃➼䛾ᅜ㝿஦ᴗ䛻ᑐ䛧䛶䚸༟㉺䛧䛯◊✲ᣐⅬ䛸䛧䛶኱Ꮫ䛸䛸䜒䛻㐃ᦠ༠ຊ䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(6) Whether or not the FERP is providing distinctive education in thefield of fusion engineering research, taking advantage of thefunction as an Inter-University Research Institute (from the 2nd midterm plan)኱Ꮫඹྠ฼⏝ᶵ㛵䛸䛧䛶䛾ᶵ⬟䜢⏕䛛䛧䛶䚸᰾⼥ྜᕤᏛศ㔝䛷䛾≉Ⰽ䛒䜛ᩍ⫱䜢ᐇ᪋䛧䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅

(7) Whether or not the FERP has been closely working with foreign
institutions by enhancing researcher exchange and collaboration,
based on the international agreements (from the 2nd mid-term plan)ᅜ㝿஺ὶ༠ᐃ䛺䛹䛻ᇶ䛵䛝䚸ᾏእ䛾◊✲ᣐⅬ䛸䛾◊✲⪅஺ὶ䚸ඹྠ◊✲䛻䜘䜚㐃ᦠ䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(8) Whether or not the FERP has contributed to creating the
research results from universities (from the 3rd mid-term plan)኱Ꮫ䛛䜙䛾◊✲ᡂᯝ๰ฟ䛻㈨䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅


Suggestion from the last
external review (2013)
1. Whether or not the FERP is serving as a COE dedicated for thefusion technology development so that the resultant technologies
could be utilized as an engineering knowledge basis
᰾⼥ྜᕤᏛศ㔝䛻䛚䛡䜛ᇶ┙ᢏ⾡㛤Ⓨ䛾 COE 䛸䛧䛶䛾ᙺ๭䜢ᯝ䛯䛧䚸䛭䛣䛷㛤Ⓨ䛥䜜䛯᭱ඛ➃ ᢏ⾡䜢ᕤᏛ䛸䛧䛶Ꮫ⾡ⓗ䛺య⣔໬䜈῝໬䛥䛫䛶䛔䜛䛛

2. Whether or not the FERP has come up with a strategy jointly with
universities and other institutions to foster human resources, inparticular young scientists who could take the lead on their fieldsof researchୡ⏺䜢䝸䞊䝗䛩䜛ⱝᡭ◊✲⪅䛾⫱ᡂ䛻ྥ䛡䛶䚸ேⓗᇶ┙䛾ᣑ඘䛸㉁ⓗྥୖ䜢ᐇ⌧䛩䜛᪂䛧䛔ே ᮦ⫱ᡂ䛾ᯟ⤌䜏䜢䚸኱Ꮫ䜔◊✲ᶵ㛵䛸㐃ᦠ䛧䛶ᵓ⠏䛧䛶䛔䜛䛛

3. Whether or not the FERP has been operated efficiently inintroducing large-scale test facilities and providing necessary staff
to establish the desirable research environment኱ᆺᶵჾ䜔ヨ㦂タഛ䛾ᑟධ䛸䚸䛭䛾䛯䜑䛾ேⓗ㓄⨨䜔ቑဨ䜢䜒㋃䜎䛘䛯◊✲⎔ቃ䛾ᩚഛ䚸⥔ ᣢ䞉⟶⌮యไ䛾ᵓ⠏䜢䛿䛛䜚䚸ຠ⋡ⓗ䛺㐠⏝䜢㐍䜑䛶䛔䜛䛛

4. Whether or not the FERP has contributed to setting the standard
for fusion energy development via making a database out of theresearch resultsᡂᯝ䜔▱ぢ䛾㞟✚໬䞉䝕䞊䝍䝧䞊䝇໬䛻䜘䜚᰾⼥ྜ䛾つ᱁䞉ᇶ‽ᵓ⠏䛻ᐤ୚䛧䛶䛔䜛䛛





1. Design Study on the Helical
Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲1. Design Study on the
Helical Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲(1) Whether or not the FERP has shown continued
progress on upgrading and refinement of the helicalo thet e 2nd mid-termd te pplan)
a )reactor design study ((from䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛾㧗ᗘ໬䞉⢭ᐦ໬䜢⥅⥆ⓗ䛻㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅䝸䜹 ᆺ᰾⼥ྜ⅔タィ 㧗ᗘ໬ ⢭ᐦᐦ໬䜢⥅⥆ⓗ䛻㐍䜑䜛䛛䠄➨ ᮇ୰ᮇィ⏬䜘䜚䠅

helicalreactorstudyis(2)TheWhetheror not the
FERP hasdesign
summarizedtheconceptualprogressing.
design of the helical fusion reactor and haslargelyembodied the numerical targets for each developmentz
Detailed
simulation for plasma operation and startup(from the 3rd mid-term plan)issuezInnovative options for engineering design䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾ᴫᛕタィ䜢䜎䛸䜑䚸ྛ㛤Ⓨㄢ㢟䛾ᩘ್┠ᶆ䜢ලయ໬䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇᮇィ⏬䜘䜚䠅
9 High-Tc conductor and joint winding

9 Liquid-metal
divertorin support
helical divertor(3) Whether
or not thehelicalfusionofreactor
design study
9
Molten-saltblanketwithgood
maintainability
and the R&D activities on major components arez
Cost analysis
closely
related with each other (from the 3rd mid-term plan)z
Exploration of smaller and sub-ignition concepts䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛸ᇶᖿᶵჾ䛾㛤Ⓨ◊✲䛸䛜㐃ື䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅





Design study on the helical fusion reactor
FFHR-d1 has been intensively carried out
FY2010 – FY2013
z 1st round:

FY2014 – FY2017
z 3rd round:

9Basic device parameters

9Construction of 3D structure
9Maintenance method of invessel components

z 2nd round:
93D design components
9Physics analysis on thecore plasma

R [m]
B [T]
V [m3]
Magnetic Energy
Fusion Power

LHD
3.9 m
3T
30 m3
0.9 GJ—z Multipath strategy
9Detailed physics analysis for
operation and startup scenario
9Cost model
9d1A, d1B, d1C, and c1

FFHR-d1
15.6 m
5.1 T
1900 m3
170 GJ
3 GW

Engineering Design of FFHR-d1
Innovative ideas
idea
ea
ass h
a
have
ha
ave been integrate
integrated
grateed(1) toto overcome
ovvercomme dmedifficulties
difficulties with 3Dff
D structure(2) toto enenhancenhancce papassiveassive safetyas(3) to improve plant efficiency
BlanketMolten salt + Ti powder+
Segmentation

Superconducting magnet
High-Tc Superconductor+
Joint Winding

Divertor
W-monoblock + Cu-alloy cooling-pipe+
Liquid metal (Sn) shower

Structural materials
Ferritic steel + ODS,
V-alloySuperconducting Magnet
Basic
hel
elicalical coil
coi windingfor LHDz Cable in Conduit
Conductor (CICC) of
Nb3Sn as ITER (or NB3Al)
CICC for ITERz Continuous winding ofhelical coil using awinding machine as LHD
helelicalical coil windingz SC coil is directly cooled
for FFHR
by liquid He

Challenging
helelicalical coil for
fo
or FF
FFHR
FH
HRH
R-d1
d1

100 kAkA
A-cclass
la
ass
HTS
H
S
conductor(helium gas cooling
g 220
0 K)
K)

me
echanical
ec
ch
han
nica
lap
p Joint

NITA coilz High Temperature
Superconductor (HTS) of
ReBCO (YBCO, GdBCO…)
z Joint winding of helicalcoil based on the lap joint
techniquez SC coil is indirectly cooled
by He gas“Joint-Winding” of FFHR-d1 Helical Coils
Helical Coils
Lift up by 0.5-1 m¾ Gas helium cooling (20 K)¾ Welding between turns¾ No need for VPI
390 turns㽢
㽢5 segments㽢2 coils= 3,900 joints
if1 day / joint(for 2coils & 2directions)
Î 3,900/4= 2.7 years

Setup of the coil casing

Breeding and Shielding Blankets

Basic

Interior design of asosolid
olid brebreedebreedereede
er blanket
blan
nkett

lanket
nket
Y. So
Y.
Someya
Som
om
meyya
m
yya,
a, IAEAIAAEA FEC
FE
EC 24
EC
4 bla
(2012) FTP/P7
P7-333 stru
P7
sstructure
tructure iin ahelicalsegmentation

tokamaktokamakfusionfusi
ion
io
on rrereactor
eac
SLIM
SLIM
SLI
M--CS
CS
K.. ToK
Tobitaobbittaoobit
ta,a, FEDF D 85(2010) 1342

z The 1st option of theJapanese tokamak DEMO
and Japanese ITER TBM
z Cooling by highlypressurized hot water of >200 atm and > 600 K

Challenging

z Use FLiNaBe (Tm ~ 600 K)
at a low pressure of a few
atm
z Powders (~Pm) ofhydrogen storage metal(e.g., Ti) are mixed
Toroidal / horizontal
zT
T-SH
SHELL
S
HELL bblanketlankett horizontal
FLiNaBeF
FLiNaBBe mixedm(toroidal segmentation)) segmentation
segmentation of thenwith Ti powder blanket moduleFLiNaBe is the New Candidate
Liquid Blanket
z High safetyz High efficiency
 Molten-salt or Liquid metalz The melting temperature ofΥ
FLiNaBe is as low as ~300Υ

Selective heating of the metalby optimizing
power is possiblepthe microwave mode

- Lower than FLiBe of m.p. ~360Υ
- Thermal efficiency improves andmaterial choice becomes widerz Metal powder (e.g. Ti) is
introduced to increasehydrogen solubility- Microwave for hydrogen recovery




Toroidally Segmented Blanket Could bea Possibility for Easy Maintenance
Helicalsegmentation

T-SH
SHELL
S
HELL
Blanket
Bla
anket
an
ket

CARDISTRY
RYY-B(T(Toroidally
Toroiddalllllyy-S
Sliced,
liced
d, HE
d,
HELically
EL llyELical
llyLinked
ed breeder blankets)(CA
CARtridges
ARttridg
idg
gees
es D
Divided
Di
ivid
iv
id
ide
deed
d an
and
InSerTeded RadiallY
Y - Blanket)

T. Goto et al., PFR 11 (2016) 2405047

J. Miyazawa et al., PFR 12 (2017)
1405017

Remote maintenance First proposal of the
Cartridge-type blankets
in high-radiation
toroidally segmented tritium for both BB and neutron
environment is an issue Breeding Blanket (BB)Shielding Blanket (SB)

Neutronics and Thermofluid Analyses
Neutronics

Thermofluid

Simulation by the MCNP code

Calculated fast neutron profiles
z Streaming and neutron
absorption by the side wall
are taken into accountz TBR > 1.10 will beachievable with FLiNaBez It will be possible to keep the temperatureof the structure materials below 550 Υ, if
the magnetic field is not very highz Deterioration of thermal conductivity athigh B is a concern

T. Tanaka et al., ISFNT-13, Kyoto (2017)

T. Murase et al., ISFNT-13, Kyoto (2017)

Divertor

Basic

ful
ulll helicaldivertorddivooptionclo
losed
sed divertor
di
orr
in
FFHR
in LHD

Challenging
novel divertorz Developed for ITER andthe 1st option of Japanese
tokamak DEMOz Cooling by pressurized
water
z Permissible heat load isdiveivertore orr ca
erto
assettebelow 10 MW/m2
foror ITER
IT
TE
ER
R
http
ht
tp://
tp
p://
///na
naka
akka
az Maintenance is difficult
www.jaea.go.jp
wwwww
w.jaea.go.j
w
jaea
jjae
a go jjpp/english
sh/iterterteer-ez A lot of radioactive wastes/divertor.html

z Proposed recently for
FFHR-d1 and c1
Insert the shower to theinboard ergodic layerz Use molten tin (Tm ~ 500 K)
shower of a few m/s of flowlliquid
iq
qui
uid
ui
d meta
metal
m
al er
ergodic
rgod
speed as an “ergodic
limiter/divertor
limiter/divertor”
z Adopt the “novel divertor”
Plasma goes to Plasmalgoes tothe inboardthe outboard-side
structure for easyside disappears also disappears
maintenanceShower of molten tinHelical Divertor

Helical Divertor
z Good exp. results in LHD
D
z Heat flux tolerable withhaslight radiation dispersionionz Cu-alloy pipes applicablelewith low neutron flux
¾ Maintenance by remotehandling is an issue

Max. heat flux is estimated at ~25 MW/m2
without radiation dispersion (or detachment)

Neutron flux is reduced to 1/10 in“Novel Divertor” with a cut in the
supporting-arms of helical coilsLiquid Tin Shower Divertor
REVOLVER-D

Shower of molten tin

Insert the shower tothe inboard ergodic layer

Reactoror-oriented Effectivelyory VOLumetricicc VERticalal DivertorDz High permissible heat load
headingz High pumping efficiency PPlasma
for the divertor
disappearsz High maintainabilityz Low costsshower
how
ho
we
er
of
of wat
water
w
tter
jets
jetts w
withz Low amount of radioactive
chainschhains
i s
insidewastesz High Safety

Plasma going tothe outboard-side
also disappears
cchainhainhainstabilizedstat bilizebili ebeddwater jetsjmoltenmolttensolder
sold
old
de
de
er jjets
ets
e
tss

(Sn
Sn
n6
60
0-Pb
Pb40)
40
0



Core Plasma Simulation

T. Goto et al., FED 89 (2014) 2451
T. Goto et al., 25th IAEA-FEC (2014)
T. Goto et al., 26th IAEA-FEC (2016)z Basis of a real-time simulation of plasma operation

control scenario was developedz A self-consistent solution of Q ~ 10 on the FFHR-d1 has
been found by a systems code “HELIOSCOPE” based on“Direct Profile Extrapolation (DPE)”
9 Consistent with MHD equilibrium/stability, neoclassical transport, Dparticle confinement, He ash contamination, and bootstrap current

Validated by reproducing
experimental data of LHD

POPCON plot achieving Q = 10 in the FFHR-d1 

Simulations
Plasma startup scenario
for FFHR-d1

Investigation of magnetic fielddistortion by ferritic steel blanket(Collaboration with ASIPP)
Pr = 1.3 (F82H blanket)

Overestimation in the present model

Q = 10Slight expansion of magnetic surfaces(adjustable by sub-helical coils)1. Design Study on the
Helical Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲(1) Whether or not the FERP has shown continued
progress on upgrading and refinement of the helical
reactor design study (from the 2nd mid-term plan)䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛾㧗ᗘ໬䞉⢭ᐦ໬䜢⥅⥆ⓗ䛻㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(2) Whether or not the FERP has summarized theconceptual design of the helical fusion reactor and has
embodied the numerical targets for each development
issue (from the 3rd mid-term pplan)䝦䝸䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾ᴫᛕタィ䜢䜎䛸䜑䚸ྛ㛤Ⓨㄢ㢟䛾ᩘ್┠ᶆ䜢ලయ໬䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇ䝸䜹䝹ᆺ
ᆺ᰾⼥ྜ⅔䛾ᴫᛕタィ䜢䜎䛸䜑䚸ྛྛ㛤Ⓨㄢ㢟䛾ᩘ್┠ᶆ䜢ලయ໬䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅

The conceptual design report of the(3) Whether or not the helical fusion reactor design study
FFHR-d1hasbeen onpublished
and concreteand the R&D
activities
major components
are
(from
the 3 mid-term
plan)closely relatedwith eachnumerical
targets
forothereach
issue
are listed.
rd䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛸ᇶᖿᶵჾ䛾㛤Ⓨ◊✲䛸䛜㐃ື䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛸ᇶᖿᶵჾ䛾㛤Ⓨ◊✲䛸䛜㐃ື䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅





The Entire Report of FERP
(FY2010-FY2015) has been Issued

z ~450 pages in totalz Including both helical reactor
design and R&D activities
z Numerical goals are also
included in the appendix





Numerical Targets are Summarized
Numerical Targets for
the Magnet Systemz Numerical targets for themagnet system, in-vessel
components, and blanket
system have beensummarized

Numerical Targets are Summarized
Numerical Targets for
the In-vessel Components

Numerical Targets for
the Blanket System






1. Design Study on the
Helical Fusion Reactor䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾タィ◊✲(1) Whether or not the FERP has shown continued
progresson upgradingrefinement
thehelicalhelicalR&D
studies
closelyand
linkedwith ofthe(from
the 2nd mid-termprogressing.
plan)reactor design
study
reactordesignareintensively䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛾㧗ᗘ໬䞉⢭ᐦ໬䜢⥅⥆ⓗ䛻㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅z
HTS magnet(2) Whether
or not the FERP has summarized thez
Molten-saltblanket(metalpowder,neutronconceptual designof thehelicalfusionreactor and has
irradiation,
HF,
Oroshhi-2)
embodied the numerical targets for each developmentz
Liquidmetal divertor((fromfrom the 3rd mid
mid-term
term p
plan)
lan))
issue
䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔䛾ᴫᛕタィ䜢䜎䛸䜑䚸ྛ㛤Ⓨㄢ㢟䛾ᩘ್┠ᶆ䜢ලయ໬䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅(3) Whether or not the helical fusion reactor design study
and the R&D activities on major components areclosely related with each other (from the 3rd mid-term plan)䝦䝸䜹䝹ᆺ᰾⼥ྜ⅔タィ䛸ᇶᖿᶵჾ䛾㛤Ⓨ◊✲䛸䛜㐃ື䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅High-Temperature Superconductor

Joint Winding
Short-sample test successfully achieved
100 kA @5 T, 20 K with 0.3 m length

13 T, f700 mm
SC magnet

Segmented
conductors(~ 30 m unit length)

Coiled sample test planned to examine
50 kA @13 T, 20 K with 6 m lengthNi melting
m
po
pott
FLiNaK with
Ti powder(0.1wt%)Hig
Highlyghly
ghly
ypermeative
Molten ssalt

V platew// Metal powder
p

Less
L
ess
permeative

H2

Schematic of theexperimental setupp㻢㼤㻝㻜㻙㻢

550Υ
10Pa-H2
1 hour㻡㼤㻝㻜㻙㻢㻢䠄㼓 㻴㻛㼓 㼂㻕䠄㼓㻙㻴㻛㼓㻙㼂㻕w/ow//o Metal powderpHydrogeninventory in the V plate䝞䝘䝆䜴䝮୰䜈䛾Ỉ⣲⵳✚㔞㔞Molten Salt with Metal Powder㻠㼤㻝㻜㻙㻢
㻟㼤㻝㻜㻙㻢
㻞㼤㻝㻜㻙㻢
㻝㼤㻝㻜㻙㻢
㻜㻲㻸㼕㻺㼍㻷

䃛㼀㼕㻙㻲㻸㼕㻺㼍㻷 㼚㼀㼕㻙㻲㼚㼀㼕㻙㻲㻸㼕㻺㼍㻷

9H
Hydrogen inventory in the V platez Molten salt generally shows low
aafter 1 hour H2 exposure decreases
hydrogen retention
when the Ti powder is addedw
z Hydrogen easily permeates to theЍ Hydrogen is successfullymaterial or outside
retained in the Ti powerЍ Micro or Nano size powder of
9 P and n denote the size of Ti
Hydrogen storage metal is added ppowdern A
to increase the hydrogen retention
A. Sagara et al., FED 89 (2014) 2114
(new idea proposed by Prof. Sagara) J. Yagi et al., 29th SOFT (2016) 

Experiments using Liquid
Metal Jets are Ready to Go
Glove box

z Glove box (Ar atmosphere)

Vacuumm chamber

MHD exp.
using PMand TIG arc

9LM jet of ~1 m length (w/ U-alloy 78 at ~100 Υ)
9MHD experimentz Vacuum chamber
9LM jet of ~0.1 m length (w/ Tin at ~300 Υ)
9high heat load experiment Ohgo, SOKENDAI D1 (2017)

moltenmolttent ssolder jetsj
(Sn60
60-Pb40)




2. R&D Study on the Fusion
Technology BasisᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲

2. R&D Study on the Fusion
Technology Basis
工 学基盤構築に向けた研究(1) Whether or not the FERP has served as a COE
dedicated for fusion technology development
核融合工学分野における基盤技術開発のCOEとしての役割を果たしているか(2) Whether or not the FERP is enhancing interdisciplinary
researches to strengthen the basis of the fusion
engineering study (from the 2nd mid-term plan)
工学研究の基礎となる学際領域の研究拡充を図っているか（第二期中期計画より）(3) Whether or not the FERP is improving the facilities forthe engineering study and enhancing the joint-use andcollaboration (from the 2nd and 3rd mid-term plans)
工学実験設備の更なる拡充と高度な共同利用·共同研究を進めているか（第二期、第三期中期計画より）(4) Whether or not the FERP is enhancing thecollaboration research by utilizing the frameworks of“Bilateral Collaboration Research” and “LHD Project
Collaboration Research” (from the 2nd mid-term plan)
双方向型共同研究、LHD計画共同研究などの制度を有効に利用し共同研究の拡充を図っているか（第二期
中期計画より）
Research Roadmap of FERP





Collaboration Network and COE
Carried out in coordination with the research promoted by Universities

Divertor 㻴㼕㼓㼔㻌㼔㼑㼍㼠㻌㼠㼑㼟㼠㻌㼍㼚㼐㻌㼍㼚㼍㼘㼥㼟㼕㼟㻌㼛㼒㻌㼔㼥㼐㼞㼛㼓㼑㼚㻌㼕㼚㻌㼟㼡㼞㼒㼍㼏㼑
Coordination research

Coordination research 㻿㻯㻌㼙㼍㼓㼚㼑㼠㻌

TohokuKagoshima

KyushuTokai(2) Large-scale highfield SC magnet
research

TI Tech

Tokyo

Osaka

SeikeiKyoto㼠㼑㼟㼠㻌㼒㼍㼏㼕㼘㼕㼠㼕㼑㼟

TohokuSSCmmagnet(3)(2)

Integrity ofjoint interfaceof SC wires

(4)

NIFS

Tokyo

TI TechKyushu(4) Long life liquidblanket research

TohokuToyama

Osaka

Kyoto

㻴㼥㼐㼞㼛㼓㼑㼚㻌㼠㼑㼟㼠㻌㼍㼚㼐㻌㼙㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻌㼑㼝㼡㼕㼜㼙㼑㼚㼠

Hydrogentransport inliquid breeder
systems
Kyushu University㻹㼍㼠㼑㼞㼕㼍㼘㻌㼟㻌㼜㼞㼛㼠㼛㼠㼥㼜㼕㼚㼓㻘㻌㼠㼑㼟㼠㼕㼚㼓㻌㼍㼚㼐㻌㼍㼚㼍㼘㼥㼟㼕㼟㻌㼑㼝㼡㼕㼜㼙㼑㼚㼠
Coordination researchMaterial
atterraate
Kyushuu

Kyoto
Tohoku

Kyoto

Shizuoka

KyushuOsaka
OsHiroshima(1) Low-activation
structural materials
research

Muroran

Hokkaido

Nagoya University
Coordination research

Akita

Hokkaido

Toyama(5) Trace tritium
Ibarakicontrol technology Shizuoka
research
KyushuNagoyaO&E Health

Ehime

Research of tritium
decontamination in
the plasma andtritium behavior in
the material

HachinoheDual-beam ion
irradiation on fusion
structural materials
Kyoto University

TsukubaHigh density
plasma exposure
to divertor
materials

Tritium

Coordination researchFukui(3) High heat flux
plasma-facing wall Shimane
research

((1
1)
(1)

Blanket

Osaka

Tokai

(5)

㻴㼑㼍㼠㻌㼍㼚㼐㻌㼙㼍㼟㼟㻌㼒㼘㼛㼣㻌㼘㼛㼛㼜㻌㼑㼝㼡㼕㼜㼙㼑㼚㼠

Tohoku University

Hokkaido

University of ToyamaStructural materials for advanced blankets of helical reactors
Thermal creep of high
HIP joining of RAFM and 9Cr-ODS
purity V-4Cr-4Ti alloys

NH2 : NIFS-HEAT-2 High purity V-4Cr-4Ti
US : US-DOE HEAT medium purity V-4Cr-4Ti
F82, JLF-1 : Reduced activation ferritic steel 䠄RAFM)
䠕Cr-ODS : Oxide Dispersion Strengthened 9Cr steel

High purity V-4Cr-4Ti high had higher ductility
but lower strength.
However, the creep strength was shown to becomparable with medium purity V-4Cr-4Ti

HIP joining caused matrix hardening andinterface softening.
Post-Weld Heat Treatment recovered to theoriginal hardness profile

LTC options for magnet systems of helical reactors
Development of high-strength
Development of indirect-cooling
Nb3Sn strand
large-current Nb3Sn conductor

9 Yield strength increases by Cu-Zn matrix
9 Tensile stress at which max. Ic obtained
increases to 200 MPa

9 Al-alloy jacket with
Friction Stir Welding
9 A 20-kA coiled sample
ready to be tested in
13-T, I700-mm magnet
9 Strengthened strand by
Cu-Nb matrix

Advancement of solid helical divertors for helical reactors
Optimization of brazing technology
High strength Cu-alloys by MA and HIP

W/BNi-6/GlidCop®.

MA time

Small Grain

The new divertor test sample fabricated by
W/BNi-6/GlidCop joining showed heat flux
resistance to 15 MW/m2

Increase in MA time resulted in fine structure andhigh strength of Cu-1Al. High radiation resistanceis expected.
Advanced liquid blanket and materials characterization technology for helical reactors
Tritium permeation barrier/electrical
Cathodolimonescence (CL) of blanket materials
insulation coating by MOCVD
for non-destructive structural characterization

Scratch tests showed degradation by thermal
cycling can be controlled by selecting CVD gas
flow rate

CL spectra of Er2O3
coating specimens
baked at different
temperatures showed
microstructural
evolution during
sintering process.

Supporting DD experiment of LHD and application to helical reactors
Shizuoka U.

DD Experimentin LHD

Ion
implantation

NIFS
monitoring

Exhaust gas
processing

H isotope ion
implantation
U. Toyama

Imaging Plate
H/D/T
retention

Surfacecontrol
Tritium glow
discharge

Isotopeseparation

Nagoya U.

GD-OES
Mass
Transfer

Isotopeseparation
Thermal Desorption
Spectroscopy

Kyushu U.

Tritium transfer
test

Electrolysis andchemical exchange

2. R&D Study on the Fusion
Technology Basis
工 学基盤構築に向けた研究(1) Whether or not the FERP has served as a COE
dedicated for fusion technology development
核融合工学分野における基盤技術開発のCOEとしての役割を果たしているか(2) Whether or not the FERP is enhancing interdisciplinary
researches to strengthen the basis of the fusion
engineering study (from the 2nd mid-term plan)
工学研究の基礎となる学際領域の研究拡充を図っているか（第二期中期計画より）(3) Whether or not the FERP is improving the facilities forthe engineering study and enhancing the joint-use andcollaboration (from the 2nd and 3rd mid-term plans)
工学実験設備の更なる拡充と高度な共同利用·共同研究を進めているか（第二期、第三期中期計画より）(4) Whether or not the FERP is enhancing thecollaboration research by utilizing the frameworks of“Bilateral Collaboration Research” and “LHD Project
Collaboration Research” (from the 2nd mid-term plan)
双方向型共同研究、LHD計画共同研究などの制度を有効に利用し共同研究の拡充を図っているか（第二期
中期計画より）

ACT2 for BNCT (Boron Neutron Capture
Ttarget – Twater (K)Therapy) Target Development

w/o ribwith rib
Heat load (MW/m2)

Proton
P
oton
ton
nb
beam
eam
m
(42 kWW, 8 x 8 cm
m2 )6.6 MW/mm2
Targ
Target
get p
plate
late
e
filled with Li

ElectronEElect
ron BeamBe
eamm

Cooling waterr
Water
er-coolederCu
u blockHeat transfer
transfsfer
sf
fer andann turbulencend
tturb
turbuleenc
ence in the V-type
rib structure (flow velocity = 2 m/s, simulation by
the Tsuji Lab. in Nagoya Univ.)coooolingolingwater inletcoooolingolingwater outlet

Inside ACT
CT
T2



2. R&D Study on the Fusion
Technology Basis

工 学基盤構築に向けた研究(1) Whether or not the FERP has served as a COE
dedicated for fusion technology development
核融合工学分野における基盤技術開発のCOEとしての役割を果たしているか(2) Whether or not the FERP is enhancing interdisciplinary
researches to strengthen the basis of the fusion
engineering study (from the 2nd mid-term plan)
工学研究の基礎となる学際領域の研究拡充を図っているか（第二期中期計画より）(3) Whether or not the FERP is improving the facilities forthe engineering study and enhancing the joint-use andcollaboration (from the 2nd and 3rd mid-term plans)
工学実験設備の更なる拡充と高度な共同利用·共同研究を進めているか（第二期、第三期中期計画より）(4) Whether or not the FERP is enhancing thecollaboration research by utilizing the frameworks of“Bilateral Collaboration Research” and “LHD Project
Collaboration Research” (from the 2nd mid-term plan)
双方向型共同研究、LHD計画共同研究などの制度を有効に利用し共同研究の拡充を図っているか（第二期
中期計画より）
Superconducting Magnet Facility forInternational Collaborations
HTS TSTC Conductor
Sample (MIT)HTS STARS
Conductor (NIFS)
FEM Model (PPPL)

JT-60SA Central Solenoid(one module) was tested at
NIFS SCM Lab.

¾ “Large-Bore High-Field Magnet Test
Facility” (13 T , I700 mm) is ready tooperate¾ MIT’s TSTC HTS conductor sample will
be tested in Feb., 2018
¾ Temp. variable refrigerator will supply
4-50 K liquid & gas helium





Oroshhi-2: various experiments are
ongoing

3TT
3T㉸ఏᑟ
3
㉸SC
㉸ఏᑟ
ఏᑟ
m
magnet
䝬
䜾g䝛䝑䝖
䝬䜾䝛䝑䝖

FLiNaK
K loop

ᆒ୍ᆶ┤
ᆒ
୍nᆶ
┤
Uniform
Un
iffo
orm
☢ሙ㡿ᇦ
☢
ሙ
㡿al
ᇦffielvertical
ve
rtica
field
d

(D
䠄745ŵŵʔ䠅
䠄7
745
7
45
5=ŵ745ŵʔʔmm)䠅 )((world’s
ld’┠ⓗ
hig
hi
highest
g
he
h䛿st
st 䠄
䠄ྠ┠ⓗ䛷䛿
䠄
ྠ┠ⓗ
ྠ
䛷䛿
䛷
mag.
field)
d)䠅
ୡ⏺
ୡ
ୡ⏺᭱ᙉ䠅
⏺᭱ᙉ䠅
⏺
᭱ᙉ䠅
᭱
ᙉ

3 T SC magnet
LiPb
Pb loopBԋ

Inventoryyy:: 12
Inventory:
120
20
2
0 L ini eachh looploo
opPipe width:
width
h: 1 iinchh:nccch oror 1.
1.55 incinch
cch
Max. flow velocity:
y: 1.5.55 m/s
Oroshhi-2
2 䠄Operational Rec
Recoverycoveeery Of
O
Separated Hydrogen and Heat Inquiry-2䠅

550
0 cm
cm 1T
䡚
䡚50cm

B

p
pe
ermanenerm
manentt
permanent
magnetmheaterH2 addition

FLiNak corrosion test
under 1 T

LLiPbὶ䜜
iPPb
bb
ὶf䜜
LiPb
lo
low
ow
w

H2 extrac
extractionet actiontion

LiPb UDV probe(Osaka Univ.)v

MHD pressure
loss on the
LiPb flow(Kyoto Univ.)

LiPb hydrogentest sub-loop

FLiNaK
FL
F
iNaK
iNa
NaaK 䝃䝤
N
䝃䝤䝹䞊
䝃䝤䝹
䝃
䝃䝤䝹䞊䝥
䝤䝹
䝤䝹
䝹䞊
䞊䝥
䞊䝥

FLiNa
FLiNaK
K(᭱㧗
sub
su
u㧗
b700
-0lo
loop
oCC)op㓄⟶(᭱㧗700
㓄
⟶(᭱㧗
⟶
㧗700
70
00
) p tube(max. ~700
00
0 Υ)
o

H2 measurement
ment



HIP: A Super-Clean Environment is኱ᆺHIP⿦⨨እほ኱ᆺHI
HIP⿦⨨እほPrepared for MA and Encapsulation
thermocouple
graphitealumina

Large globe box

Inside the pressure vessel኱ᆺ䝤䝻䞊䝤䝪䝑䜽䝇

HIP
P (H
(Hot
Hot Isostatic Pressing)device㧗㟼Ỉᅽຍᅽ⿦⨨vacuumpumpingmping
line
TIG torch
Nipperpp

HIP capsulemanufacture
manufaufa
actu
ture devic
device㧗⣧ᗘ㔠ᒓᒓ䜹䝥䝉䝹䝹⬺Ẽᑒධ⿦⨨Inside the HIP capsulemanufacture devic
deviceRotatingstage

㧗⣧ᗘ㔠ᒓ䜹䝥䝉䝹⬺Ẽᑒධ⿦⨨



ACT2: EB Control System andCooling System have been Improved
Tungstentarget before
irradiation

Tungstentarget after
irradiation

ACT2

rradiation
adiatiion
thermometer

ElectronEle
lectronGun
polarizing lensap
aparture
parturelimiter

Electron beam profile is
Gaussian with the
FWHM ~ 10 mm

scan

W-Cu alloy divertor
target mockup test

apartureEBscanning
scann
nin
area

beam dump
cooling tubee

thermocouple

irradiated region
specimen

TEM and FIB: Powerful tool by
the combination
Tungsten alloy after 0.08 – 0.16 sirradiation at 230 MW/m2 in ACT2
irradiat

FIB
Focus
Focusedocusedd Io
Ionn Beam(NB
NB5000
NB
00
00)
0

0.08
0
.08
8s
irradiation
micrro g
micro
grain
ra
ain
structurerecrystalization

TEM
TrransmTransmission
ansm
nsm
miission
iss Electron Microscopy(JEM
M-2800)-MicccroMicroroograin

0.08
0
.08
8s
irradiation

cracking

0.16
0
.16
6s
irradiation
Thermal Creep Test Facilities
Eight thermal creep test facilities
were installed
High temperature (~1173K)High vacuum (1x10-7Pa)
Small specimens(5mm gauge length)(for testing advanced materials)
Precise temperature and stresscontrol is necessary

Creep Strain for V-4Cr-4Ti

Rupture Time vs Stressfor V-4Cr-4Ti

2. R&D Study on the Fusion
Technology Basis

工 学基盤構築に向けた研究(1) Whether or not the FERP has served as a COE
dedicated for fusion technology development
核融合工学分野における基盤技術開発のCOEとしての役割を果たしているか(2) Whether or not the FERP is enhancing interdisciplinary
researches to strengthen the basis of the fusion
engineering study (from the 2nd mid-term plan)
工学研究の基礎となる学際領域の研究拡充を図っているか（第二期中期計画より）(3) Whether or not the FERP is improving the facilities forthe engineering study and enhancing the joint-use andcollaboration (from the 2nd and 3rd mid-term plans)
工学実験設備の更なる拡充と高度な共同利用·共同研究を進めているか（第二期、第三期中期計画より）(4) Whether or not the FERP is enhancing thecollaboration research by utilizing the frameworks of“Bilateral Collaboration Research” and “LHD Project
Collaboration Research” (from the 2nd mid-term plan)
双方向型共同研究、LHD計画共同研究などの制度を有効に利用し共同研究の拡充を図っているか（第二期
中期計画より）
“Bilateral Collaboration Research” and“LHD Project Collaboration Research
Examples of bilateral collaboration researchz Divertor simulation in GAMMA-10 (Tsukuba U.)z Edge plasma study in Heliotron-J (Kyoto U.)z Co-deposition layer research in QUEST (Kyushu U.)
z Thermo-fluid study of liquid metal in the first wall in

the Institute of Laser Engineering (Osaka Univ.)z Tritium behavior in plasma facing materials (U. of

Toyama)z PWI for neutron irradiated materials (Tohoku U.)“Bilateral Collaboration Research” and“LHD Project Collaboration Research
Examples of LHD project collaborationz In-situ diagnostics with LIBS (UCSD and Kanazawa U.)z PWI with gas impurities (Hokkaido U.)
Plasma-wallz TDS technology in (Shizuoka U.)
Interactions
z Irradiation effects on hydrogen retention (Osaka U.)
z Linear plasma device in hot laboratory (Nagoya U. and Tohoku U. )z Tungsten coated graphite (U. of Toyama)z Advancement of tungsten alloys (Tohoku U.)
Plasma facing
components/z Advanced copper alloys (Kyoto U./Tohoku U.)
materialsz Heat conversion in divertor system (Kyoto U. )z Liquid lithium technology from IFMIF/EVEDA project (Kyoto U.)
Blankettechnologyz Oxide film coating for blanket application (Tokai U. and TIT)
z Advanced helical winding for HTS (Meiji U.)
Magnettechnologyz Advanced helical winding for Nb-Sn (Sophia U.)z Cross-section for charge exchange reaction of tungsten (Niigata U.)
A&M
z Molecular detrapping (Toho U.)
z Isotope effect of dynamics of tritium transport (Shizuoka U.)
Tritium sciencez Isotope separation of hydrogen (Nagoya U.)
and technologyz Biological effects of low-level tritium (Hiroshima U.)
z Environmental tritium transport (Kyushu U.)
z Tritium removal from LHD (U. of Toyama)2. R&D Study on the Fusion
Technology Basis (contd.)ᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(5) Whether or not the FERP has served as a COE to contribute to
the international activities including ITER and BA, jointly with
universities (from the 2nd mid-term plan)ᅜ㝿⇕᰾⼥ྜᐇ㦂⅔ཬ䜃䛂ᖜᗈ䛔䜰䝥䝻䞊䝏䛃➼䛾ᅜ㝿஦ᴗ䛻ᑐ䛧䛶䚸༟㉺䛧䛯◊✲ᣐⅬ䛸䛧䛶኱Ꮫ䛸䛸䜒䛻㐃ᦠ༠ຊ䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(6) Whether or not the FERP is providing distinctive education in thefield of fusion engineering research, taking advantage of thefunction as an Inter-University Research Institute (from the 2nd midterm plan)኱Ꮫඹྠ฼⏝ᶵ㛵䛸䛧䛶䛾ᶵ⬟䜢⏕䛛䛧䛶䚸᰾⼥ྜᕤᏛศ㔝䛷䛾≉Ⰽ䛒䜛ᩍ⫱䜢ᐇ᪋䛧䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅

(7) Whether or not the FERP has been closely working with foreign
institutions by enhancing researcher exchange and collaboration,
based on the international agreements (from the 2nd mid-term plan)ᅜ㝿஺ὶ༠ᐃ䛺䛹䛻ᇶ䛵䛝䚸ᾏእ䛾◊✲ᣐⅬ䛸䛾◊✲⪅஺ὶ䚸ඹྠ◊✲䛻䜘䜚㐃ᦠ䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(8) Whether or not the FERP has contributed to creating the
research results from universities (from the 3rd mid-term plan)኱Ꮫ䛛䜙䛾◊✲ᡂᯝ๰ฟ䛻㈨䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅Collaboration with ITER
9SC magnet and cryo system- ITER-TF conductor joint samples (final specification)
tested and confirmed low-resistance requirement- Cryo-system simulation code C-PREST

9Neutral Beam Injection (NBI)- Beam simulation and experiments in NIFS test stand

PerformanceP
erformance test
test ofof a
ITER-TF joint sample at
NIFS

Sim
Simulation results of theMass flow rate from LHe
reservoir to the compressor
suction, by C-PREST at NIFS

3D-beamlet simulation including secondary
charged particles
Collaboration with BA
9JT-60SA- SC magnet testing Î One of the actual CS coils tested

9IFERC (DEMO-R&D)- Specimen size effects on thermal creep
p tests- Tritium control in DEMO
- System code
- PWI experiment in JET

Performance tests of
the JT-60SA CS model 9IFMIF-EVEDA
and module coils- Hydrog
Hydrogen
gen monitoring
monitorin in Liquid Li

Hydrogen monitoring and trapping with
Y-Nb for flowing Li

Specimen thickness effects on
creep rupture for RAFM (Reduced
Activation Ferrite Materials)



The Action Plan for Tokamak DEMO
has been Issued by the Joint Core Teamz 15 major items are listedz Requests on SC, Blanket,
Divertor, Material, and Helical
System are closely related tothe activities on the FERP




An Example of Possible NIFS
Contribution to the Action Plan




Progress in Joining Technology
EBW: Electron-beam welding, HIP: Hot-isostatic
tic pressingpg
25L
5 x 50w
5 x 2.86t mm

Reinforcement of the ferritic steel material by joining with ODS

StrongEBW of V alloy and hastelloy with or w/o Ni or Cu filler

Absorbed energy at a RT
z The ductility of V-alloy/Hastelloy joint
drastically improves with Cu filler

Application to advanced blankets

Tensile strength and elongationz The strength of RAFM/ODS/RAFM recovers
after PWHT (Post-Weld-Heat-Treatment)

Application to enhancing DEMO
blanket performanceCollaboration on Atomic andMolecular Database
9NIFS is providing thelargest database to GENIE

JPN
NIFS

- GENIE is the worldwide search engine ofatomic and molecular database- Organized by DCN (IAEA)

䠭䠯䠰

CHN

USA

CRAAMD

NIST

DCN
KOR
NFRI
KAERI

((AM
A & PMI Data Center Network)k)

UK

AtomicAt
and Molecular Datata
Unit, IAEA

ADAS

RUS
Kurchatov
Inst.

GER
FZJ

http://www-aamdis.iiaea.o
http://www-amdis.iaea.org/GENIE/
org/GENIE/

9NIFS as a DCN member
contributes to Data
Evaluation activities. 

2. R&D Study on the Fusion
Technology Basis (contd.)ᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(5) Whether or not the FERP has served as a COE to contribute to
the international activities including ITER and BA, jointly with
universities (from the 2nd mid-term plan)ᅜ㝿⇕᰾⼥ྜᐇ㦂⅔ཬ䜃䛂ᖜᗈ䛔䜰䝥䝻䞊䝏䛃➼䛾ᅜ㝿஦ᴗ䛻ᑐ䛧䛶䚸༟㉺䛧䛯◊✲ᣐⅬ䛸䛧䛶኱Ꮫ䛸䛸䜒䛻㐃ᦠ༠ຊ䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(6) Whether or not the FERP is providing distinctive education in thefield of fusion engineering research, taking advantage of thefunction as an Inter-University Research Institute (from the 2nd midterm plan)኱Ꮫඹྠ฼⏝ᶵ㛵䛸䛧䛶䛾ᶵ⬟䜢⏕䛛䛧䛶䚸᰾⼥ྜᕤᏛศ㔝䛷䛾≉Ⰽ䛒䜛ᩍ⫱䜢ᐇ᪋䛧䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅

(7) Whether or not the FERP has been closely working with foreign
institutions by enhancing researcher exchange and collaboration,
based on the international agreements (from the 2nd mid-term plan)ᅜ㝿஺ὶ༠ᐃ䛺䛹䛻ᇶ䛵䛝䚸ᾏእ䛾◊✲ᣐⅬ䛸䛾◊✲⪅஺ὶ䚸ඹྠ◊✲䛻䜘䜚㐃ᦠ䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(8) Whether or not the FERP has contributed to creating the
research results from universities (from the 3rd mid-term plan)኱Ꮫ䛛䜙䛾◊✲ᡂᯝ๰ฟ䛻㈨䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅Variety of Studies are being Carried
Out by Doctoral Studentsᾮయ䝅䞁䝏䝺䞊䝅䝵䞁ᾮᾮయ䝅䞁䝏䝺䞊䝅䝵䞁
䞁
䜹䜴䞁
䜹䜴
䜹䜴䞁䝍
䜴䞁䝍
䞁䝍
㼀 ᐃ

HA
HAZ

He,, T2O

᤼䜺
᤼䜺䝇
᤼
䜺䝇 He
He
ฎ
ฎ⌮
⌮⣔䜈
䜈
ฎ⌮⣔䜈

WM 316L

Dissimilar
issimilmi aarr-memetalmetbonding
b
bon
nding
nd
dn
ng
g
WHT
PWHT
HAZ P
HAZ
(Fu,
F82H
F
82HSOKENDAI)
316LW
M 316L
WM

M
MHD
pressure loss ofof LiPLiPb
Pb
in double bending
g pipe(Nakamura, Kyoto Univ.)

CuO
C
uO

He,, T2

䝞䝤䝷䞊䠎
䝞
䝞䝤
䝤䝷䞊
䝤䝷
䝤
䝷䞊䠎
T2O
Oᤕ㞟
ᤕ㞟

Ỉ

Ỉ

He
He

T2 TF

He䝪䞁䝧

F82H

Neu
NeutronN
utrontirradiation
di
on m
on
molten
mo
oltte
olte
te
en
n sa
ssaltt(Ku
Kumagai
umag
gai
gai,
aii,
SOKENDAI)
T T

AmBe
⥺※

H T22,, TTFF
He,
䝞䝤䝷䞊䠍
䝞䝤
䝞
䝞䝤䝷
䝤
䝤䝷
䝷䞊䠍
TTFᤕ㞟
TF
ᤕ㞟
㞟

FL NaaKFLi
FLiNaKaK~50
5000oC
~500
300cm
m3

T

↷ᑕ䝏䜵䞁䝞䞊
䠄䜹䞊䝪䞁䝤䝻䝑䜽୰ᛶᏊ཯ᑕᮦ䠄䜹䞊䝪䞁䝤䝻䝑䜽䠅䠇䝫䝸䜶䝏䝺䞁䝤䝻䝑䜽䠅

Liquidiquid memetal
etaal jet wit
witha chain inside

w/o TIG arc

with TIG arc

Liqu
Liquiduid
d metalmeetta
al divertor(Ohgogoo, SOKENDAI)z Dissimilar-metal bonding (Fu, SOKENDAI (2017))
z High-temperature superconductor (Terazaki,
SOKENDAI (2017))
z MHD pressure drop in the double bending pipe
(Nakamura, Kyoto Univ.)z Neutron irradiation on molten salt (Kumagai,
SOKENDAI)z MHD effect on the liquid metal jet (Ohgo,
SOKENDAI)
z…



Human Resource Development~ Whether or not FERP is bringing up young researchers
who can support long-range growth of international fusion studyேᮦ⫱ᡂ ࠥ᰾⼥ྜ◊✲䛾㛗ᮇⓗ䛺Ⓨᒎ䜢ᨭ䛘䜛ᅜ㝿ⓗ䛻ά㌍䛷䛝䜛ேᮦ䛾⫱ᡂ䛻㈉⊩䛧䛶䛔䜛䛛

59

39

Number of titles

9 98 papers (39 by NIFS students, and 59 by University students)
have been published by the students through the collaboration
with FERP from FY2013.
40
20
02013 2014 2015 2016
Year

2017

Bachelor thesis/reserches
Master thesis
Doctor thesis

Breakdown of published papers

Academic degrees including NIFS
collaboration results2. R&D Study on the Fusion
Technology Basis (contd.)ᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(5) Whether or not the FERP has served as a COE to contribute to
the international activities including ITER and BA, jointly with
universities (from the 2nd mid-term plan)ᅜ㝿⇕᰾⼥ྜᐇ㦂⅔ཬ䜃䛂ᖜᗈ䛔䜰䝥䝻䞊䝏䛃➼䛾ᅜ㝿஦ᴗ䛻ᑐ䛧䛶䚸༟㉺䛧䛯◊✲ᣐⅬ䛸䛧䛶኱Ꮫ䛸䛸䜒䛻㐃ᦠ༠ຊ䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(6) Whether or not the FERP is providing distinctive education in thefield of fusion engineering research, taking advantage of thefunction as an Inter-University Research Institute (from the 2nd midterm plan)኱Ꮫඹྠ฼⏝ᶵ㛵䛸䛧䛶䛾ᶵ⬟䜢⏕䛛䛧䛶䚸᰾⼥ྜᕤᏛศ㔝䛷䛾≉Ⰽ䛒䜛ᩍ⫱䜢ᐇ᪋䛧䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅

(7) Whether or not the FERP has been closely working with foreign
institutions by enhancing researcher exchange andcollaboration, based on the international agreements (from the 2nd
mid-term plan)ᅜ㝿஺ὶ༠ᐃ䛺䛹䛻ᇶ䛵䛝䚸ᾏእ䛾◊✲ᣐⅬ䛸䛾◊✲⪅஺ὶ䚸ඹྠ◊✲䛻䜘䜚㐃ᦠ䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(8) Whether or not the FERP has contributed to creating the
research results from universities (from the 3rd mid-term plan)኱Ꮫ䛛䜙䛾◊✲ᡂᯝ๰ฟ䛻㈨䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅Collaboration based on international
agreements etc.
US–Japan Collaborationz Joint project of TITAN and PHENIXz Workshops (Reactor design and PWI/HHF and others)z Personal exchanges
China –Japan, Korea-Japan Collaborationsz JWG (J-C)
z JCM (J-K)
z A3 foresight program (J-C-K) 䠄JSPS)z Post-CUP (J-C) (NIFS internal budget)
IEA Stellarator/Heliotron
IEA PWI
IAEA Coordinated Research Project and Workshops
OthersCollaboration in US-J Joint Projects
Technological interaction between US-Japan Joint Project
and NIFS collaboration
TITAN : Tritium, Irradiation and Thermofluid (FY2007-2012)
PHENIX : PFC evaluation by tritium plasma, heat, neutron
irradiation (FY2013-2018)

TPE
T
PE in
in INL
INL

PlasmaP
lasma ddeviceevice iinnOarai Center,
Tohoku University((TITAN/PHENIX)T(NIFS collaboration
with Nagoya U.)

MTORM
TOR inin UCLAUCLA ((TITAN)
TITAN) O
Orishhi-2
rish
hhi-2 inin NIFS
NIFS

Plasma exposure to neutronirradiated materials


Thermofluid of liquid breeders
in magnetic fields

Framework of Collaboration with China
㻲㼅

㻞㻜㻜㻝

㻞㻜㻜㻞

㻞㻜㻜㻟

㻞㻜㻜㻠

㻞㻜㻜㻡

㻞㻜㻜㻢

㻞㻜㻜㻣

㻞㻜㻜㻤

JSPS-CAS Core University Program(Plasma, Engineering, Simulation)

㻞㻜㻜㻥

㻞㻜㻝㻜

㻞㻜㻝㻝

㻞㻜㻝㻞

㻞㻜㻝㻟

㻞㻜㻝㻠

㻞㻜㻝㻡

㻞㻜㻝㻣

㻞㻜㻝㻢

post-CUP (NIFS internal program)(Plasma, Engineering, Simulation)
JSPS/NSFC/NRF-A3 Foresight
Program (Fusion Physics)㻹㻱㼄㼀㻛㻹㻻㻿㼀㻌㻭㼓㼞㼑㼑㼙㼑㼚㼠㻌㻼㼞㼛㼓㼞㼍㼙 㻔㻶㼃㻳㻕㻔㻼㼘㼍㼟㼙㼍㻘㻌㻱㼚㼓㼕㼚㼑㼑㼞㼕㼚㼓㻘㻌㻿㼕㼙㼡㼘㼍㼠㼕㼛㼚㻕“Post-CUP” continued based on NIFS internal budget with smaller size than CUP
Major platform for fusion engineering collaboration between Japanese and Chinese
Institutes and Universities (material, blanket, tritium)
J/C/K/ A3-Foresight Program started in 2012 for 5 years
Mostly physics but includes plasma-wall interactions and A&M
MEXT/MOST agreement program (JWG) started in 2008 including fusion engineering
NIFS&JAEA - ASIPP&SWIP program(LHD/JT-60SA/EAST/HL2A, reactor design, magnet etc)

2. R&D Study on the Fusion
Technology Basis (contd.)ᕤᏛᇶ┙ᵓ⠏䛻ྥ䛡䛯◊✲(5) Whether or not the FERP has served as a COE to contribute to
the international activities including ITER and BA, jointly with
universities (from the 2nd mid-term plan)ᅜ㝿⇕᰾⼥ྜᐇ㦂⅔ཬ䜃䛂ᖜᗈ䛔䜰䝥䝻䞊䝏䛃➼䛾ᅜ㝿஦ᴗ䛻ᑐ䛧䛶䚸༟㉺䛧䛯◊✲ᣐⅬ䛸䛧䛶኱Ꮫ䛸䛸䜒䛻㐃ᦠ༠ຊ䜢ᅗ䛳䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(6) Whether or not the FERP is providing distinctive education in thefield of fusion engineering research, taking advantage of thefunction as an Inter-University Research Institute (from the 2nd midterm plan)኱Ꮫඹྠ฼⏝ᶵ㛵䛸䛧䛶䛾ᶵ⬟䜢⏕䛛䛧䛶䚸᰾⼥ྜᕤᏛศ㔝䛷䛾≉Ⰽ䛒䜛ᩍ⫱䜢ᐇ᪋䛧䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅

(7) Whether or not the FERP has been closely working with foreign
institutions by enhancing researcher exchange and collaboration,
based on the international agreements (from the 2nd mid-term plan)ᅜ㝿஺ὶ༠ᐃ䛺䛹䛻ᇶ䛵䛝䚸ᾏእ䛾◊✲ᣐⅬ䛸䛾◊✲⪅஺ὶ䚸ඹྠ◊✲䛻䜘䜚㐃ᦠ䜢㐍䜑䛶䛔䜛䛛䠄➨஧ᮇ୰ᮇィ⏬䜘䜚䠅(8) Whether or not the FERP has contributed to creating the
research results from universities (from the 3rd mid-term plan)኱Ꮫ䛛䜙䛾◊✲ᡂᯝ๰ฟ䛻㈨䛧䛶䛔䜛䛛䠄➨୕ᮇ୰ᮇィ⏬䜘䜚䠅


40
30
20
10
0
2012

2014

Number of awards

Numbers

50

20
15
10
5
0

2016

2018

Other publications

8

180

7

160

6

140

5
4
3

120
100
80
60

2

40

1

20

0

0

Total amount of budgets (M yen)

Presentations atinternational
conferences
Presentations atdomestic
conferences
Refereed papers

60

Number of budget titles

Total number of budget titles (bars)
and amounts (lines) during FY2013FY2017 for non-NIFS researchers.

year

Year



Publications
Publications in 2013-2017: 440 in total
9393 on R&D(67 on SC magnet & Cryogenics, 57 on
Low activation materials,
81 on Blanket & First wall, 158 on
Divertor, 41 on Tritium & Safety)
955 on Reactor Design(21 on Concept & System design, 13 onCore plasma control,
23 on Plant equipment & related
technology)
9226 written by non-NIFS staffs
998 written by students

Future Plan
91. Execution and completion of the 3rd Midterm Plan by FY2021-

Engineering design for prototype magnet and blanket systems for helical
reactors
Establishing research roadmap toward helical reactors
Establishing NIFS as a COE for fusion engineering by collaboration using thefacilities installed
Contribution to creation of research outcomes by Universities

92. Application of research results to DEMO Action Plan and C&R
93. Further enhancement of the research- Pursuing more attractive helical reactor concepts
Passive safety
Load following
Social receptivity- R&D contributing to formulating post-LHD concepts





㻾㼑㼒㼑㼞㼑㼚㼏㼑㼟㻌㻌㻌㼀㼍㼎㼘㼑㻌㼛㼒㻌㻱㼢㼍㼘㼡㼍㼠㼕㼛㼚㻌㻾㼑㼟㼡㼘㼠㼟㻌㼒㼛㼞㻌㼠㼔㼑㻌㻞㻜㻝㻣㻌㻱㼤㼠㼑㼞㼚㼍㼘㻌㻼㼑㼑㼞㻌㻾㼑㼢㼕㼑㼣㻌䇾㻲㼡㼟㼕㼛㼚㻌㻱㼚㼓㼕㼚㼑㼑㼞㼕㼚㼓㻌㻾㼑㼟㼑㼍㼞㼏㼔㻌㻼㼞㼛㼖㼑㼏㼠䇿㻌

Table of Evaluation Results for the 2017 External Peer Review"Fusion Engineering Research Project"䊠. Points for Evaluation
1.㻌Design Study on the Helical Fusion Reactor(1)Whether or not the FERP has shown continued progress on upgrading and refinement of the helical reactor design study(2)Whether or not the FERP has summarized the conceptual design study of the helical fusion reactor and embodied the numerical targets
for each development issue(3)Whether or not the design study of the helical fusion reactor and the R&D activities of the major components are closely related witheach other

2.R&D Study on the Fusion Technology Basis(1) Whether or not the FERP has served as a COE dedicated for the fusion technology development.
(2) Whether or not the FERP is enhancing the interdisciplinary researches to strengthen the basis of the fusion engineering study(3) Whether or not the FERP is improving the facilities for the fusion engineering study and enhancing the joint-use and collaboration(4)Whether or not the FERP is enhancing the collaboration research by utilizing the frameworks of “Bilateral Collaboration Research” and“LHD Project Collaboration Research”(5)Whether or not the FERP has served as a COE to contribute to the international activities including ITER and BA, jointly with
(6)Whether or not the FERP is providing distinctive education in the field of fusion engineering research, taking advantage of the function
as an inter-university research institute(7)Whether or not the FERP has been closely cooperating with foreign institutions by enhancing researcher exchange and collaboration,
based on the international agreements(8)Whether or not the FERP has contributed to creating the research results from universities

䊡. Tabele of Evaluation

Number of persons

Point of Evaluation 1. Design Study on the Helical Fusion Reactor 2. R&D Study on the Fusion Technology Basis

(1)

(2)

(3)

(1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

㻢

㻞

㻠

㻝㻜

㻞

㻣

㻢

㻡

㻟

㻢

㻠

㻥

㻝㻝

㻣

㻢

㻣

㻤

㻝㻝

㻝㻜

㻝㻞

㻥

㻥

㻞

㻠

㻡

㻝

㻤

㻞

㻜

㻞

㻞

㻞

㻟

㻜

㻜

㻝

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻝

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻜

㻠㻚㻞㻠

㻟㻚㻤㻤

㻟㻚㻤㻞

㻠㻚㻡㻟

㻟㻚㻢㻡

㻠㻚㻞㻥

㻠㻚㻟㻡

㻠㻚㻝㻤

㻠㻚㻜㻢

㻠㻚㻞㻠

㻟㻚㻥㻠

Score

䠑
(Extremely highlycommmendable)䠐(Highly commendable)䠏(Commendable)䠎(Adequate)䠍(Inadequate)

Average Score䈜㼀㼔㼑㻌㼑㼢㼍㼘㼡㼍㼠㼕㼛㼚㻌㼞㼑㼟㼡㼘㼠㻌㼕㼟㻌㼍㻌㼏㼛㼙㼎㼕㼚㼍㼠㼕㼛㼚㻌㼛㼒㻌㼠㼔㼑㻌㼞㼑㼟㼡㼘㼠㼟㻌㼛㼒㻌㼐㼛㼙㼑㼟㼠㼕㼏㻌㼏㼛㼙㼙㼕㼠㼠㼑㼑㻌㼙㼑㼙㼎㼑㼞㼟㻌㻔㻝㻟㻌㼜㼑㼞㼟㼛㼚㼟㻕㻭㼢㼑㼞㼍㼓㼑㻌㻿㼏㼛㼞㼑㻌㻌㻌㼍㼚㼐㻌㼒㼛㼞㼑㼕㼓㼚㻌㼏㼛㼙㼙㼕㼠㼠㼑㼑㻌㼙㼑㼙㼎㼑㼞㼟㻌㻔㻠㻌㼜㼑㼞㼟㼛㼚㼟㻕㻚

㻡㻚㻜㻜
㻠㻚㻣㻡
㻠㻚㻡㻜
㻠㻚㻞㻡
㻠㻚㻜㻜
㻟㻚㻣㻡
㻟㻚㻡㻜
㻟㻚㻞㻡
㻟㻚㻜㻜
㻞㻚㻣㻡
㻞㻚㻡㻜
㻞㻚㻞㻡
㻞㻚㻜㻜
㻝㻚㻣㻡
㻝㻚㻡㻜
㻝㻚㻞㻡
㻝㻚㻜㻜
㻜㻚㻣㻡
㻜㻚㻡㻜
㻜㻚㻞㻡
㻜㻚㻜㻜

4.24

㻝㻚㻔㻝㻕

4.53

4.29 4.35 4.18
4.06 4.24 3.94

3.88 3.82

㻝㻚㻔㻞㻕

㻝㻚㻔㻟㻕

3.65

㻞㻚㻔㻝㻕

㻞㻚㻔㻞㻕

㻞㻚㻔㻟㻕

㻼㼛㼕㼚㼠㻌㼛㼒㻌㻱㼢㼍㼘㼡㼍㼠㼕㼛㼚

㻞㻚㻔㻠㻕

㻞㻚㻔㻡㻕

㻞㻚㻔㻢㻕

㻞㻚㻔㻣㻕

㻞㻚㻔㻤㻕



































㻵㼚㼠㼑㼞㻙㼁㼚㼕㼢㼑㼞㼟㼕㼠㼥㻌㻾㼑㼟㼑㼍㼞㼏㼔㻌㻵㼚㼟㼠㼕㼠㼡㼠㼑㻌㻯㼛㼞㼜㼛㼞㼍㼠㼕㼛㼚㻌㻺㼍㼠㼕㼛㼚㼍㼘㻌㻵㼚㼟㼠㼕㼠㼡㼠㼑㼟㻌㼛㼒㻌㻺㼍㼠㼡㼞㼍㼘㻌㻿㼏㼕㼑㼚㼏㼑㼟㻌㻺㼍㼠㼕㼛㼚㼍㼘㻌㻵㼚㼟㼠㼕㼠㼡㼠㼑㻌㼒㼛㼞㻌㻲㼡㼟㼕㼛㼚㻌㻿㼏㼕㼑㼚㼏㼑㻌㻟㻞㻞㻙㻢㻌㻻㼞㼛㼟㼔㼕㻙㼏㼔㼛㻘㻌㼀㼛㼗㼕㻘㻌㻳㼕㼒㼡㻘㻌㻡㻜㻥㻙㻡㻞㻥㻞㻘㻌㻶㼍㼜㼍㼚㻌㼔㼠㼠㼜㻦㻛㻛㼣㼣㼣㻚㼚㼕㼒㼟㻚㼍㼏㻚㼖㼜㻛㻌