Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO
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- 作者：Yoshinori Kawamuraa ; kawamura.yoshinori@jaea.go.jp" class="auth_mail" title="E-mail the corresponding author ; Hisashi Tanigawaa ; Takanori Hirosea ; Mikio Enoedaa ; Satoshi Satob ; Kentaro Ochiaic ; Chikara Konnob ; Yuki Edaob ; Takumi Hayashib ; Tsuyoshi Hoshinoc ; Masaru Nakamichic ; Hiroyasu Tanigawac ; Hiroshi Nishia ; Satoshi Suzukia ; Koichiro Ezatoa ; Yohji Sekia ; Toshihiko Yamanishic
- 关键词：Demo Blanket ; WCCB-TBM ; F82H ; Advanced breeder ; Advanced multiplier ; Tritium
- 刊名：Fusion Engineering and Design
- 出版年：2016
- 出版时间：1 November 2016
- 年：2016
- 卷：109-111
- 期：part_PB
- 页码：1637-1643
- 全文大小：2630 K
文摘
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Thermo-hydraulic calculation in the TBM at the water ingress event has been done.
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Shielding calculations for the ITER equatorial port #18 were conducted by using C-lite model.
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Prototypic pebbles of Be17Ti2 and Be12V had a good oxidation property similar to Be12Ti pebble.
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Li rich Li2TiO3 pebbles were successfully fabricated using the emulsion method by controlling sintering atmosphere.
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New tritium production/recovery experiments at FNS have been started by using ionization chamber as on-line gas monitor.