Microstructure evolution in MA956 neutron irradiated in ATR at 328 °C to 4.36 dpa-Reference-Cited by-同舟云学术

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Microstructure evolution in MA956 neutron irradiated in ATR at 328 °C to 4.36 dpa

Published:2020-05 Issue: Volume:533 Page:152094
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Zhang Zhexian,Saleh Tarik A.,Maloy Stuart A.,Anderoglu Osman

Funder

U.S. Nuclear Regulatory Commission

Nuclear Energy University Program

Publisher

Elsevier BV

Subject

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

Reference80 articles.

1. Nuclear Fuel Safety Criteria Technical Review;Beck,2012

2. Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies-Operational Behaviour;International Atomic Energy Agency,2012

3. State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels;Oecd-Nea,2018

4. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

5. Material selection for accident tolerant fuel cladding;Pint;Metall. Mater. Trans. E.,2015

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