Technical considerations on tritium breeding blanket systems for a fusion power reactor-Reference-Cited by-同舟云学术

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Technical considerations on tritium breeding blanket systems for a fusion power reactor

Published:1989-01 Issue: Volume:8 Page:219-226
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kuroda T.,Sato K.,Suzuki T.,Tone T.,Seki M.

Publisher

Elsevier BV

Subject

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

Reference6 articles.

1. Design studies of tokamak power reactor in JAERI;Tone,1985

2. S. Mori, T. Kuroda et al., High tritium breeding blanket, ibid. [2], E.7.1-J

3. Blanket comparison and selection study;Smith,1984

4. International Tokamak Reactor: Phase One,1982

5. International Tokamak Reactor: Phase Two A,1983

Cited by 5 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. Three-dimensional analyses of candidate blanket designs for the compact tokamak reactor concept;Progress in Nuclear Energy;1995-01

2. Design study of helium-solid suspension cooled blanket and divertor plate for a tokamak power reactor;Fusion Engineering and Design;1994-08

3. Preliminary Design of a Solid Particulate Cooled Blanket for the Steady State Tokamak Reactor (SSTR);Fusion Technology;1992-05

4. Ceramic sphere-pac breeder design for fusion blankets;Fusion Engineering and Design;1991-12

5. Solid breeder blanket design and tritium breeding;Fusion Engineering and Design;1991-12

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