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-Reference-Cited by-同舟云学术

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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

Published:2017-04 Issue: Volume:486 Page:391-401
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Balooch Mehdi,Olander Donald R.,Terrani Kurt A.,Hosemann Peter,Casella Andrew M.,Senor David J.,Buck Edgar C.

Funder

U.S. Department of Energy, Office of Nuclear Energy under DOE

Publisher

Elsevier BV

Subject

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

Reference21 articles.

1. NAA-SR;Gylfe,1960

2. Uranium–zirconium hydride fuel properties

3. Transient hydride fuel behavior in LWRs

4. Terminal Solid Solubility of Hydrogen in Unalloyed Zirconium by Differential Scanning Calorimetry

Cited by 2 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. Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap;Kerntechnik;2022-10-13

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

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