Zobrazeno 1 - 10
of 34
pro vyhledávání: '"Homma, Yuuki"'
Publikováno v:
IEEE Transaction on Plasma Science. 48(6):1799-1803
In a demonstration (DEMO) reactor, mitigation of the large heat load on the divertor target to the below material and engineering limits is a key requirement for operation. Systems modeling is used to design entire fusion power plants and, therefore,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::c820a6c867b3b1453e5356f8fca9dbb8
https://repo.qst.go.jp/records/79403
https://repo.qst.go.jp/records/79403
Autor:
Tobita, Kenji, Hiwatari, Ryoji, Sakamoto, Yoshiteru, Someya, Yoji, Asakura, Nobuyuki, Uto, Hiroyasu, Miyoshi, Yuuya, Tokunaga, Shinsuke, Homma, Yuuki, Kakudate, Satoshi, Nakajima, Noriyoshi
Publikováno v:
Fusion Science and Technology. 75:372-383
This paper summarizes the evolution of Japanese DEMO design studies in a retrospective manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently working on the conceptual study of a steady state DEMO (JA DEMO) with
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::44c930c3f2a1f3551c07e3b189f0f064
https://repo.qst.go.jp/records/76084
https://repo.qst.go.jp/records/76084
Autor:
Hiwatari, Ryoji, Katayama, Kazunari, Nakamura, Makoto, Miyoshi, Yuuya, Aoki, Akira, Asakura, Nobuyuki, Uto, Hiroyasu, Homma, Yuuki, Tokunaga, Shinsuke, Nakajima, Noriyasu, Someya, Yoji, Sakamoto, Yoshiteru, Tobita, Kenji, Special Design Team for Fusion DEMO, Joint
Publikováno v:
Fusion Engineering and Design. 143:259-266
The conceptual design of Japan’s fusion demonstration plant (JA DEMO) is now being developed. In this paper, an overall plant system concept related to tritium handling in the water-cooling system is developed to give a concrete shape to the presen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::a507c9a4093b91f22d99e76d17495d4c
https://repo.qst.go.jp/records/75612
https://repo.qst.go.jp/records/75612
核燃焼プラズマから排出される熱流とプラズマ粒子の処理を行うダイバータの設計は、核融合炉設計の最重要な課題である。現在、核融合出力1.5 GWレベルで主半径8.5 m の原型炉を想定し
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::bde46cb1ac8c73c6e0922ad21e7cf944
https://repo.qst.go.jp/records/79435
https://repo.qst.go.jp/records/79435
Autor:
Someya, Yoji, Matsuyama, Akinobu, Aiba, Nobuyuki, Kato, Mitsuya, Homma, Yuuki, Asakura, Nobuyuki, Uto, Hiroyasu, Miyoshi, Yuuya, Kakudate, Satoshi, Hiwatari, Ryoji, Sakamoto, Yoshiteru, Tobita, Kenji
原型炉プラントの安全上の特徴に基づく合理的な安全確保方針案の策定に向けて、炉内トリチウムインベントリの同定と冷却水喪失事象等の安全解析を通して様々なディスラプションシ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::aff57455ae3383dfc66c84c895386a78
https://repo.qst.go.jp/records/77787
https://repo.qst.go.jp/records/77787
Autor:
Yamoto, Shohei, Hoshino, Kazuo, Homma, Yuki, Nakano, Tomohide, Hayashi, Nobuhiko, Homma, Yuuki
Publikováno v:
Contributions to Plasma Physics. 60(5-6)
In order to study the potential impurity seeding operation regime of the future fusion devices, the first application of the integrated divertor code SONIC to the Ar + Ne mixed‐impurity seeding operation of JT‐60SA steady‐state high‐β plasma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::a78440aeea4de9ed2226ea0781c7ae26
https://repo.qst.go.jp/records/79619
https://repo.qst.go.jp/records/79619
Autor:
Hoshino, Kazuo, Asakura, Nobuyuki, Tokunaga, Shinsuke, Homma, Yuuki, Shimizu, Katsuhiro, Sakamoto, Yoshiteru, Tobita, Kenji, Special, Design Team for Fusion DEMO Joint
Publikováno v:
Fusion Engineering and Design. 124:352-355
The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with the fusion power of 1.5 GW. Due to the high impurity radiation power (80% of the exhausted power),the full detachment at the inner target and the parti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::66e0d3f46c53040f34ff49ae78a7721f
https://repo.qst.go.jp/records/48415
https://repo.qst.go.jp/records/48415
Autor:
Homma, Yuki, Hoshino, Kazuo, Yamoyo, Shohei, Asakura, Nobuyuki, Tokunaga, Shinsuke, Hatayama, Akiyoshi, Sakamoto, Yoshiteru, Hiwatari, Ryoji, Tobita, Kenji, Special Design Team for Fusion DEMO, Joint, Homma, Yuuki
Publikováno v:
Nuclear Materials and Energy. 12:323-328
Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for the DEMO fusion reactor design, because the divertor target has to sustain large fluence of incident particles, composed mainly of fuel ions and seed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::1b05ea7b4d54fbfe8212b5dc8dba5971
https://repo.qst.go.jp/records/48961
https://repo.qst.go.jp/records/48961
Autor:
Someya, Yoji, Sakamoto, Yoshiteru, Hiwatari, Ryoji, Aiba, Nobuyuki, Nakajima, Noriyoshi, Asakura, Nobuyuki, Uto, Hiroyasu, Kakudate, Satoshi, Miyoshi, Yuuya, Homma, Yuuki
原型炉設計合同特別チームでは、文部科学省の原型炉開発総合戦略タスクフォースの策定したアクションプランに沿って、日本の原型炉概念設計を実施している。原型炉の目標は、数十
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::41bb1bfc105daaed6e8160d77eaae9f0
https://repo.qst.go.jp/records/77785
https://repo.qst.go.jp/records/77785
Autor:
Miyoshi, Yuuya, Hiwatari, Ryoji, Someya, Yoji, Homma, Yuuki, Tokunaga, Shinsuke, Asakura, Nobuyuki, Sakamoto, Yoshiteru
原型炉において周辺プラズマの一部は熱流束として磁力線に沿って移動、第一壁へと到達し、第一壁を構成するブランケット筐体の表面熱負荷の要因となる。表面熱負荷は磁力線と筐体
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::6011511be119c4ca58291bab4e475924
https://repo.qst.go.jp/records/77780
https://repo.qst.go.jp/records/77780