Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO

被引:27
作者
Kawamura, Yoshinori [1 ]
Tanigawa, Hisashi [1 ]
Hirose, Takanori [1 ]
Enoeda, Mikio [1 ]
Sato, Satoshi [2 ]
Ochiai, Kentaro [3 ]
Konno, Chikara [2 ]
Edao, Yuki [2 ]
Hayashi, Takumi [2 ]
Hoshino, Tsuyoshi [3 ]
Nakamichi, Masaru [3 ]
Tanigawa, Hiroyasu [3 ]
Nishi, Hiroshi [1 ]
Suzuki, Satoshi [1 ]
Ezato, Koichiro [1 ]
Seki, Yohji [1 ]
Yamanishi, Toshihiko [3 ]
机构
[1] Japan Atom Energy Agcy, 801-1 Mukoyama, Naka, Ibaraki 3110193, Japan
[2] Japan Atom Energy Agcy, 2-4 Shirane Shirakata, Tokai, Ibaraki 3191195, Japan
[3] Japan Atom Energy Agcy, 2-166 Omotedate Obuchi, Aomori 0393212, Japan
关键词
Demo Blanket; WCCB-TBM; F82H; Advanced breeder; Advanced multiplier; Tritium; TRITIUM RELEASE; FABRICATION; MODULE; JAPAN;
D O I
10.1016/j.fusengdes.2015.11.002
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The development of a water cooled ceramic breeder (WCCB) test blanket module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and development of DEMO blanket, R&D has been performed on the module fabrication technology, breeder and multiplier pebble fabrication technology, tritium production rate evaluation, as well as structural and safety design activities. The fabrication of full-scale first wall, side walls, breeder pebble bed box and back wall was completed, and assembly of TBM with box structure was successfully achieved. Development of advanced breeder and multiplier pebbles for higher chemical stability was continued for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium transport simulation technology, investigation of the TBM neutron measurement technology and the evaluation of the tritium production and recovery test using D-T neutron in the fusion neutron source (FNS) facility has been performed. This paper provides an overview of the recent achievements of the development of the WCCB Blanket in Japan. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:1637 / 1643
页数:7
相关论文
共 21 条
[1]  
Aldama L D, 2004, FENDL 2 1 UPDATE EVA
[2]   Steam-chemical reactivity for irradiated beryllium [J].
Anderl, RA ;
McCarthy, KA ;
Oates, MA ;
Petti, DA ;
Pawelko, RJ ;
Smolik, GR .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :750-756
[3]  
Enoeda M, 2003, NUCL FUSION, V43, P1837, DOI 10.1088/0029-5515/43/12/026
[4]   Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan [J].
Enoeda, Mikio ;
Tanigawa, Hisashi ;
Hirose, Takanori ;
Suzuki, Satoshi ;
Ochiai, Kentaro ;
Konno, Chikara ;
Kawamura, Yoshinori ;
Yamanishi, Toshihiko ;
Hoshino, Tsuyoshi ;
Nakamichi, Masaru ;
Tanigawa, Hiroyasu ;
Ezato, Koichiro ;
Seki, Yohji ;
Yoshikawa, Akira ;
Tsuru, Daigo ;
Akiba, Masato .
FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) :1363-1369
[5]  
Hoshino T., 2015, FUSION ENG DES UNPUB
[6]   EVALUATION OF TRITIUM RELEASE PROPERTIES OF ADVANCED TRITIUM BREEDERS [J].
Hoshino, Tsuyoshi ;
Ochiai, Kentaro ;
Edao, Yuki ;
Kawamura, Yoshinori .
FUSION SCIENCE AND TECHNOLOGY, 2015, 67 (02) :386-389
[7]   Development of fabrication technologies for advanced breeding functional materials For DEMO reactors [J].
Hoshino, Tsuyoshi ;
Nakamichi, Masaru .
FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) :486-492
[8]   Development of advanced tritium breeding material with added lithium for ITER-TBM [J].
Hoshino, Tsuyoshi ;
Kato, Kenichi ;
Natori, Yuri ;
Oikawa, Fumiaki ;
Nakano, Natsuko ;
Nakamura, Mutsumi ;
Sasaki, Kazuya ;
Suzuki, Akihiro ;
Terai, Takayuki ;
Tatenuma, Katsuyoshi .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :684-687
[9]   Research and development of the tritium recovery system for the blanket of the fusion reactor in JAEA [J].
Kawamura, Y. ;
Isobe, K. ;
Iwai, Y. ;
Kobayashi, K. ;
Nakamura, H. ;
Hayashi, T. ;
Yamanishi, T. .
NUCLEAR FUSION, 2009, 49 (05)
[10]   Effect of sweep gas species on tritium release behavior from lithium titanate packed bed during 14 MeV neutron irradiation [J].
Kawamura, Yoshinori ;
Ochiai, Kentaro ;
Hoshino, Tsuyoshi ;
Kondo, Keitaro ;
Iwai, Yasunori ;
Kobayashi, Kazuhiro ;
Nakamichi, Masaru ;
Konno, Chikara ;
Yamanishi, Toshihiko ;
Hayashi, Takumi ;
Akiba, Masato .
FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) :1253-1257