Present status of high heat flux experiments in relation to fusion reactors
Creators
- 1. Tokyo Univ., (Japan). Faculty of Engineering
Description
Many researches and developments related to high heat flux machinery and equipment such as the first wall, diverter-limiter and beam dump of a fusion reactor have been in progress. For the purpose of elucidating the effect that unsteady thermal load exerts on the machinery and equipment at the time of disruption, the simulation experiments using electron beam or ion beam as heat sources have been carried out. Regarding high heat flux heat removal, there are many experiments on beam dumps. As the materials for high heat flux machinery and equipment, the use of bonded materials is promising, and the research and development of graphite-metal bonded materials for the first walls and limiters, and W-Cu bonded material for diverter walls have been advanced. In this paper, the present status of these research and development is outlined. In the research and development of nuclear fusion, the attainment of critical plasma is imminent, and the next stage apparatuses are investigated concretely. Their main mission is to attain self ignition and long burning. The first wall and the diverter-limiter are used under severe environment, and their reliability and soundness demand the research and development hereafter. The loading condition and problems of the machinery and equipment around plasma are discussed. (Kako, I.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.29.855Abstract (Japanese)
核融合炉における第1壁、ダイバータ・リミタ、ビームダンプ等の高熱流束機器開発に関連した多くの研究開発が進められている。ディスラプション時の非定常熱負荷が機器に与える影響を明らかにする目的で、電子ビームやイオンビームを熱源とした模擬実験が行われている。高熱流束除熱に関しては、ビームダンプについての実験が多い。高熱流束機器用材料としては、接合材料の使用が有望であり第1壁・リミタ用として黒鉛・金属接合材、ダイバータ壁用としてW・Cu接合材等の研究開発が進められている。本稿では、これら研究開発の現状について概観する。(著者)Additional details
Additional titles
- Original title (Japanese)
- 核融合炉における高熱流束実験の現状
Identifiers
- DOI
- 10.3327/jaesj.29.855;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 29
- Journal Issue
- 10
- Journal Page Range
- p. 855-863
- ISSN
- 0004-7120
- CODEN
- NGEGAL
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54004005
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DIVERTORS; FIRST WALL; HEAT FLUX; HEAT TRANSFER; JOINTS; LIMITERS; PLASMA DISRUPTION; SIMULATION; THERMONUCLEAR REACTOR MATERIALS; THERMONUCLEAR REACTORS
- Descriptors DEC
- ENERGY TRANSFER; MATERIALS; THERMONUCLEAR REACTOR WALLS
Optional Information
- Notes
- This record replaces 19064941