Neutronic research studies on fusion reactor blanket/shielding-Reference-Cited by-同舟云学术

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Neutronic research studies on fusion reactor blanket/shielding

Published:1988-01 Issue: Volume:7 Page:323-333
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Iguchi T.,Nakazawa M.,Oka Y.,Furuta K.,Kondo S.

Publisher

Elsevier BV

Subject

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

Reference23 articles.

1. Fusion nuclear systems design and analysis;Oka;Fusion Engrg. Des.,1989

2. Neutron spectra and tritium production-rate measurements in one-dimensional LiF slab geometry as a fusion reactor blanket benchmark experiment;Iguchi,1980

3. A benchmark experiment on tritium production and radiation heating in the LiF assembly;Iguchi;Nucl. Technol./Fus.,1983

4. Measurements of tritium production-rate distribution in simulated blanket assemblies at the FNS;Maekawa,1983

5. Measurement of 7Li(n, n′α)T cross section between 13.3 and 14.9 MeV;Maekawa,1986

Cited by 1 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. The University of Tokyo;Fusion Technology;1990-03

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