Finite element based stress analysis of graphite component in high temperature gas cooled reactor core using linear and nonlinear irradiation creep models-Reference-Cited by-同舟云学术

Finite element based stress analysis of graphite component in high temperature gas cooled reactor core using linear and nonlinear irradiation creep models

Published:2015-10 Issue: Volume:292 Page:32-38
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mohanty Subhasish^ORCID,Majumdar Saurindranath

Funder

U.S. Nuclear Regulatory Commission

U.S. Department of Energy

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

Reference23 articles.

1. Radiation creep of graphite: an introduction;Blackstone;J. Nucl. Mater.,1977

2. Modeling Mechanical Behavior of a Prismatic Replaceable Reflector Block. INL/EXT-09-15868;Bratton,2009

3. Irradiation induced creep behavior of H-451 graphite;Burchell;J. Nucl. Mater.,2008

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

5. H-451 Graphite Irradiation Creep Design Model; Revision 1;DOE/HTGR–88097-Rev.1,1988

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