Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior-Reference-Cited by-同舟云学术

Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior

Published:2014-12 Issue: Volume:280 Page:27-36
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Uwaba Tomoyuki,Mizuno Tomoyasu,Nemoto Junichi,Ishitani Ikuo,Ito Masahiro

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

Reference22 articles.

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4. Thermal performance of fast reactor type uranium-plutonium oxide fuel pins at beginning-of-life conditions. Japan Nuclear Cycle Development Institute Report, JNC TN9400 2001-080, 2001;Inoue,2001

5. Fuel pellet relocation behavior in fast reactor Uranium-Plutonium mixed oxide fuel pin at beginning of life. Japan Nuclear Cycle Development Institute Report, JNC TN9400 99-070, 1999;Inoue,1999

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