Bending testing and characterization of surrogate nuclear fuel rods made of Zircaloy-4 cladding and aluminum oxide pellets-Reference-Cited by-同舟云学术

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Bending testing and characterization of surrogate nuclear fuel rods made of Zircaloy-4 cladding and aluminum oxide pellets

Published:2016-10 Issue: Volume:479 Page:470-482
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Hong^ORCID,Wang Jy-An John

Funder

Office of Nuclear Regulatory Research, the US Nuclear Regulatory Commission

US Department of Energy

Publisher

Elsevier BV

Subject

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

Reference22 articles.

1. General Standards for All Packages, §43(f) in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation for Radioactive Material;NRC,2010

2. A Method for Determining the Spent-fuel Contribution to Transport Cask Containment Requirements;Sanders,1992

3. PNNL Stress/Strain Correlation for Zircaloy;Geelhood,2008

4. Fatigue design basis for Zircaloy components;O'Donnell;Nucl. Sci. Eng.,1964

5. Low-cycle fatigue properties of Zircaloy-2 cladding;Pettersson;J. Nucl. Mater.,1975

Cited by 3 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. Simulation of dynamic characteristics of NHR200-II fuel assembly;Nuclear Engineering and Design;2021-08

2. High burn-up spent nuclear fuel transport reliability investigation;Nuclear Engineering and Design;2018-04

3. Experimental Study on Surrogate Nuclear Fuel Rods Under Reversed Cyclic Bending;Fatigue and Fracture Test Planning, Test Data Acquisitions and Analysis;2017-04-01

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