Assessment report of research and development activities in FY2014; Activity "Fusion Research and Development" (Result evaluation)

Fusion Research and Development Directorate

JAEA-Evaluation 2016-001, 128 Pages, 2016/03

JAEA-Evaluation-2016-001.pdf:33.25MB

Japan Atomic Energy Agency (hereinafter referred to as "JAEA") asked the assessment committee, "Evaluation Committee of Research and Development Activities for Fusion" (hereinafter referred to as "Committee") for result evaluation of "Research and Development of the Technical System for Extraction of Fusion Energy," in accordance with "General Guideline for the Evaluation of Government R&D Activities" by Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology " and "Regulation on Conduct for Evaluation of R&D Activities" by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Fusion Research and Development Directorate (hereinafter referred to as "FRDD") during the period from April 2010 to November 2014. The Committee evaluated the management and research activities of the FRDD based on the explanatory documents prepared by the FRDD, the oral presentations with questions-and-answers by the Director General and the Deputy Director Generals.

Design of seismic isolation for International Thermonuclear Experimental Reactor

Nakahira, Masataka; Takeda, Nobukazu; Tada, Eisuke

Jishin Kogaku Nyusu, (169), p.23 - 27, 1999/11

no abstracts in English

Thermal-hydraulic characteristics in a tokamak vacuum vessel of fusion reactor after transient events occurred

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1321 - 1327, 1997/00

no abstracts in English

Post-mortem analysis of HIP bonded first wall panel made of SS316 and DS-Cu after high heat flux testing

Hatano, Toshihisa; Fukaya, Kiyoshi; Dairaku, Masayuki; Kuroda, Toshimasa*; Takatsu, Hideyuki

Fusion Technology 1996, 0, p.511 - 514, 1996/00

no abstracts in English

Development of high power gyrotrons

*; Imai, Tsuyoshi

Shingaku Giho, 94(405), p.27 - 33, 1994/12

no abstracts in English

None

Ogawa, Masao*

PNC TJ1607 91-001, 14 Pages, 1991/03

PNC-TJ1607-91-001.pdf:0.38MB

no abstracts in English

Plasma physics and controlled nuclear fusion research; Reactor systems

Nuclear Fusion, 15(2), p.325 - 326, 1975/02

no abstracts in English

Controlled tehrmonuclear fusion

; *; M.G.Trocheris*

Nihon Genshiryoku Gakkai-Shi, 5(8), p.687 - 692, 1963/00

https://doi.org/10.3327/jaesj.5.687

no abstracts in English

Progress in procurement of remote handling equipment for ITER Blanket maintenance

Takeda, Nobukazu; Tanigawa, Hisashi; Ueno, Kenichi; Maruyama, Takahito; Noguchi, Yuto; Kakudate, Satoshi

no journal, , 

In the vacuum vessel of the ITER, dose rate is very high (250 Gy/h) even during the plasma shutdown. Therefore, in-vessel components such as blanket and divertor must be maintained by remote handling. Procurement of the remote handling system of the blanket is allocated to Japan and the JAEA is performing the final design of it toward handover to the ITER Organization scheduled in 2020. This report shows progress of the final design activity. In the final design, the major part of the systems are more detailed and the tools for welding and cutting of blanket pipes are newly designed. In the same time, feasibility of operation scenario is confirmed by system analyses such as the reliability, availability, maintainability and inspectability analysis and structural analysis. By these activities, it is confirmed that the main components whose manufacturing contract will be awarded in this year can be fabricated without any concern and will be handed over to the ITER Organization in 2020 as planned.

Progress on design and prototyping of I&C systems for ITER diagnostics in Japan

Yamamoto, Tsuyoshi; Hatae, Takaki; Yatsuka, Eiichi; Takeuchi, Masaki; Ogawa, Hiroaki; Kitazawa, Sin-iti; Imazawa, Ryota; Ishikawa, Masao; Kawano, Yasunori; Itami, Kiyoshi

no journal, , 

Japan Atomic Energy Agency is developing control and data acquisition systems for poloidai polarimeter, edge Thomson scattering system, divertor impurity monitor, IR thermography and micro fission chamber in ITER project. We developed supervisory control system, which coordinates internal devices such as detectors and laser system following discharge sequence, leading other domestic agencies. Supervisory system configures measurement parameters and performs consistency check between the parameters. We also developed sequence control function to coordinate control programs for measurement and auxiliary devices complying to ITER standards and guidelines. A flowchart conversion tool was developed. The conversion tool reduced troubles in the program codes. It also makes changes of control logic flexible. We also developed prototype data acquisition system communicating with a central control simulator. The prototype demonstrates that our system design was valid.