A new method for solving the fission gas diffusion equations with time-varying diffusion coefficient and source term considering recrystallization of fuel grains-Reference-Cited by-同舟云学术

A new method for solving the fission gas diffusion equations with time-varying diffusion coefficient and source term considering recrystallization of fuel grains

Published:2019-08 Issue: Volume:20 Page:100686
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Zhao Yunmei,Zhang Jingyu,Ding Shurong

Funder

National Natural Science Foundation of China

National Key Research and Development Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference30 articles.

1. Suzuki M. and Saitou H., 2003. Light water reactor fuel analysis code FEMAXI-6 (Ver. 1). Detailed structure and user's manual.

2. Fission product induced swelling of U–Mo alloy fuel;Kim;J. Nuclear Mater.,2011

3. Swelling under irradiation of MgO pellets containing americium oxide: the ECRIX-H irradiation experiment;Lamontagne;J. Nuclear Mater.,2011

4. MATPRO: a Handbook of Materials Properties For Use in the Analysis of Light Water Reactor Fuel Rod Behavior;MacDonald,1976

5. Re-solution of fission gas–A review: part I. Intragranular bubbles;Olander;J. Nuclear Mater.,2006

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