Estimation of the maximum permissible burnup of uranium carbide fuel pins from the aspect of fuel-clad compatibility under in-pile simulated conditions-Reference-Cited by-同舟云学术

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Estimation of the maximum permissible burnup of uranium carbide fuel pins from the aspect of fuel-clad compatibility under in-pile simulated conditions

Published:1972-10 Issue:2 Volume:22 Page:326-333
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nishio Gunji,Watanabe Hitoshi,Shimokawa Junichi

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. Ceramic Fuel Elements;Holden,1966

2. Karbidische Kernbrennstoffe für schnelle Brutreaktoren;Kummerrer;KFK-1111,1969

3. Interaction between Uranium Carbides and Liquid Sodium with Small Oxygen Content;Watanabe;J. Nucl. Mater.,1971

4. Compatibility of Uranium Carbide Fuels with Cladding Materials;Elkins,1964

5. Carburization of Austenitic Stainless Steel by Uranium Carbides in Sodium;Webb,1963

Cited by 2 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. Tests on experimental fuel elements containing carbide fuel, irradiated in the BOR-60 reactor to burn-ups of 3 and 7%;Soviet Atomic Energy;1975-07

2. Kinetics of carbon transfer governing compatibility between uranium carbide and stainless steel bonded with sodium;Journal of Nuclear Materials;1973-05

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