Corrosion behavior of irradiated oxide fuel pellets in high temperature water-Reference-Cited by-同舟云学术

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Corrosion behavior of irradiated oxide fuel pellets in high temperature water

Published:1996-09 Issue:2-3 Volume:232 Page:240-247
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Une K.,Kashibe S.

Publisher

Elsevier BV

Subject

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

Reference15 articles.

1. Proc. Int. Topical Meeting on LWR Fuel Performance;Johnson,1991

2. Proc. Int. Topical Meeting on LWR Fuel Performance;Davies,1991

3. Proc. Int. Topical Meeting on LWR Fuel Performance;Armijo,1994

4. Proc. Int. Topical Meeting on LWR Fuel Performance;Lin,1994

5. Fuel Performance and Fission Product Release Studies for Defected Fuel Elements

Cited by 5 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. Contribution of Energetically Reactive Surface Features to the Dissolution of CeO2 and ThO2 Analogues for Spent Nuclear Fuel Microstructures;ACS Applied Materials & Interfaces;2014-07-31

2. Spent fuel canister for geological repository: Inner material requirements and candidates evaluation;Journal of Nuclear Materials;2008-05

3. A conceptual model for the fuel oxidation of defective fuel;Journal of Nuclear Materials;2007-06

4. Post-irradiation examination of high burnup Mg doped UO2 in comparison with undoped UO2, Mg–Nb doped UO2 and Ti doped UO2;Journal of Nuclear Materials;2001-08

5. On the role of grain boundary diffusion in fission gas release;Journal of Nuclear Materials;2001-02

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