Blanket Concept of Water-Cooled Lithium Lead with Beryllium for the SlimCS Fusion DEMO Reactor-Reference-Cited by-同舟云学术

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Blanket Concept of Water-Cooled Lithium Lead with Beryllium for the SlimCS Fusion DEMO Reactor

Published:2011 Issue: Volume:6 Page:2405053-2405053
ISSN:1880-6821
Container-title:Plasma and Fusion Research
language:en
Short-container-title:Plasma and Fusion Research

Author:

UTOH Hiroyasu¹,TOBITA Kenji¹,SOMEYA Youji¹,TAKASE Haruhiko¹,ASAKURA Nobuyuki¹

Affiliation:

1. Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan

Publisher

Japan Society of Plasma Science and Nuclear Fusion Research

Subject

Condensed Matter Physics

Link

http://www.jstage.jst.go.jp/article/pfr/6/0/6_0_2405053/_pdf

Reference8 articles.

1. Compact DEMO, SlimCS: design progress and issues

2. [2] Y. Someya, 26th Symposium on Fusion Technology (SOFT).

3. [3] W. W. Engle, K-1693, Union Carbide Corporation, Computing Technology Center (1967).

4. [4] K. Maki et al., JAERI-M91-072 (1991).

5. [5] K. Shibata et al., JAERI 1319 (1990).

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. Study on the Li Mass Loss From LTZO in the Blanket;IEEE Transactions on Plasma Science;2024

2. Influence of modified neutron emission spectrum on tritium production performance in blanket systems with NBI-heated deuterium plasma;Fusion Engineering and Design;2018-11

3. Gas absorption and discharge behaviors of lead-lithium;Fusion Engineering and Design;2014-10

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