Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO-Reference-Cited by-同舟云学术

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

Published:2016-11 Issue: Volume:109-111 Page:1637-1643
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kawamura Yoshinori,Tanigawa Hisashi,Hirose Takanori,Enoeda Mikio,Sato Satoshi,Ochiai Kentaro,Konno Chikara,Edao Yuki,Hayashi Takumi,Hoshino Tsuyoshi,Nakamichi Masaru,Tanigawa Hiroyasu,Nishi Hiroshi,Suzuki Satoshi,Ezato Koichiro,Seki Yohji,Yamanishi Toshihiko

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference21 articles.

1. Design and technology development of solid breeder blanket cooled by supercritical water in Japan;Enoeda;Nucl. Fusion,2003

2. R&D status on water cooled ceramic breeder blanket technology;Enoeda;Fusion Eng. Des.,2012

3. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules;Tanigawa;Fusion Eng. Des.,2008

4. Research and development of tritium recovery system for blanket of fusion reactor in JAEA;Kawamura;Nucl. Fusion,2009

5. Recent progress in safety assessments of Japanese water-cooled solid breeder test blanket module;Tsuru;Fusion Eng. Des.,2008

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