Ab initio study of He, Ne, Ar, Kr incorporation in zirconium carbide-Reference-Cited by-同舟云学术

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Ab initio study of He, Ne, Ar, Kr incorporation in zirconium carbide

Published:2020-06 Issue: Volume:534 Page:152154
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sun Dan,Li Ruihuan,Ding Jianhua,Zhang Pengbo,Zhao Jijun

Funder

National Natural Science Foundation of China

Fundamental Research Funds for the Central Universities in China

Natural Science Fund Project of China

Natural Science Foundation of the Jiangsu Higher Education Institutions of China

Dalian Maritime University, China

Publisher

Elsevier BV

Subject

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

Reference44 articles.

1. The challenges associated with high burnup and high temperature for UO2 TRISO-Coated Particle Fuel;Petti,2005

2. Properties and Characteristics of ZrC, Volume 2 of Comprehensive Nuclear Materials;Jackson,2012

3. Technology Roadmap Update for Generation IV Nuclear Energy Systems;Behar,2014

4. ‘‘High Temperature Gas Cooled Reactor Fuels and Materials’’, TECDOC-1645;International Atomic Energy Agency,2010

5. Properties of zirconium carbide for nuclear fuel applications;Katoh;J J. Nucl. Mater.,2013

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. A gasket design suitable for helium circuits of generation IV Gas-Cooled reactors;Annals of Nuclear Energy;2024-06

2. The formation energy and interaction energy of point defects in ZrC;Journal of Nuclear Materials;2021-12

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