Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan-Reference-Cited by-同舟云学术

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Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan

Published:2011-10 Issue:9-11 Volume:86 Page:2265-2268
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Hirose Takanori,Tanigawa Hisashi,Yoshikawa Akira,Seki Yohji,Tsuru Daigo,Yokoyama Kenji,Ezato Koichiro,Suzuki Satoshi,Enoeda Mikio,Akiba Masato

Publisher

Elsevier BV

Subject

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

Reference13 articles.

1. Design and technology development of solid breeder blanket cooled by supercritical water in Japan

2. Progress of Design and R&D of Water Cooled Solid Breeder Test Blanket Module

3. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

4. Effects of Tube Drawing on Structural Material for ITER Test Blanket Module

5. R&D of a Li2TiO3pebble bed for a test blanket module in JAEA

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Effect of hydrogen on corrosion properties of reduced activation ferritic/martensitic steel, F82H;Fusion Engineering and Design;2019-09

2. Laser welding of fusion relevant steels for the European DEMO;Fusion Engineering and Design;2018-11

3. Functional materials for breeding blankets—status and developments;Nuclear Fusion;2017-08-16

4. Evolution of the ITER program and prospect for the next-step fusion DEMO reactors: status of the fusion energy R&D as ultimate source of energy;Journal of Nuclear Science and Technology;2013-04

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