The mechanical behavior and reliability prediction of the HTR graphite component at various temperature and neutron dose ranges-Reference-Cited by-同舟云学术

The mechanical behavior and reliability prediction of the HTR graphite component at various temperature and neutron dose ranges

Published:2014-09 Issue: Volume:276 Page:9-18
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Fang Xiang,Yu Suyuan,Wang Haitao,Li Chenfeng

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference21 articles.

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3. A revised description of graphite irradiation induced creep;Davies;J. Nucl. Mater.,2008

4. PBMR graphite core structures fitness for purpose management strategy. Management of ageing in graphite reactor cores;Davies;R. Soc. Chem. Spec. Publ.,2007

5. The various creep models for irradiation behavior of nuclear graphite;Fang;Nucl. Eng. Des.,2012

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