Transient hydride fuel behavior in LWRs-Reference-Cited by-同舟云学术

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Transient hydride fuel behavior in LWRs

Published:2009-07 Issue:2 Volume:392 Page:192-199
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Terrani Kurt A.,Seifried Jeffrey E.,Olander Donald R.

Publisher

Elsevier BV

Subject

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

Reference17 articles.

1. F. Ganda, E. Greenspan, Plutonium incineration capability of hydride versus MOX fuel in PWR, in: Proceedings of the Global ’05, Tsukuba, Japan, October 2005.

2. A. Sommer, W. Dennison, NAA-SR-5066, 1960.

3. Thermal properties of zirconium hydride

4. Thermophysical properties of uranium-zirconium alloys

5. Chemical Thermodynamics of Uranium;Grenthe,2004

Cited by 12 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. Estimation of Fracture Toughness for ε Zirconium Hydride by Vickers Microhardness Indentation Method;JOM;2021-09-21

2. Comprehensive modeling of hydrogen transport and accumulation in titanium and zirconium;Nuclear Materials and Energy;2020-05

3. Performance evaluation and post-irradiation examination of a novel LWR fuel composed of U0.17ZrH1.6 fuel pellets bonded to Zircaloy-2 cladding by lead bismuth eutectic;Journal of Nuclear Materials;2017-04

4. Irradiation effects on thermal properties of LWR hydride fuel;Journal of Nuclear Materials;2017-04

5. Hydride fuel irradiation in MITR-II: Thermal design and validation results;Nuclear Engineering and Design;2014-10

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