Tritium breeding performance of a self-cooled water based blanket-Reference-Cited by-同舟云学术

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Tritium breeding performance of a self-cooled water based blanket

Published:1987-01 Issue:2 Volume:4 Page:211-222
ISSN:0167-899X
Container-title:Nuclear Engineering and Design. Fusion
language:en
Short-container-title:Nuclear Engineering and Design. Fusion

Author:

Embrechts M.J.,Steiner D.,Varsamis G.,Deutsch L.,Gierszewski P.

Publisher

Elsevier BV

Subject

General Engineering

Reference30 articles.

1. Blanket comparison and selection study final report;Smith;Argonne National Laboratory Report, ANL/FFP/84-1,1984

2. Overview of the blanket comparison and selection study;Smith;Fusion Technology,1985

3. Design of self-cooled, liquid-metal blankets for tokamak and tandem mirror reactors;Cha;Fusion Technology,1985

4. Helium-cooled blanket designs;Wong;Fusion Technology,1985

Cited by 3 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. Properties of concentrated aqueous lithium nitrate solutions and applications to fusion reactor design;Fusion Engineering and Design;1989-01

3. Aqueous tritium breeding blanket with natural lithium;Fusion Engineering and Design;1989-01

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