Fission gas release in FBR MOX fuel irradiated to high burnup-Reference-Cited by-同舟云学术

Fission gas release in FBR MOX fuel irradiated to high burnup

Published:2005-11 Issue:2-3 Volume:346 Page:244-252
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Maeda Koji,Katsuyama Kozo,Asaga Takeo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference19 articles.

1. A.H. Booth, A method for calculating fission gas diffusion from UO2 and its application to the X-2-f loop test/Atomic Energy of Canada Ltd., Chalk River, Ontario, Canada, Report AECL-496 (1957).

2. A new fission-gas release model

3. EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM

4. Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels

5. Rim structure formation of isothermally irradiated UO2 fuel discs

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