Failure Predictions for Graphite Reflector Bricks in the Very High Temperature Reactor with the Prismatic Core Design

Author:

Singh GyanenderORCID,Fok Alex,Mantell Susan

Funder

DOE

Nuclear Energy University Program

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

Reference20 articles.

1. A Technology Roadmap for Generation IV Nuclear Energy Systems, U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 03-GA50034, December 2002.

2. Abaqus Documentation, Dassault Systemes Simulia Corp., Providence, RI, USA, 2013.

3. Elastic crack growth in finite elements with minimal remeshing;Belytschko;Int. J. Numer. Meth. Eng.,1999

4. Department of Energy (DOE), Evaluation of Graphite Stresses, Reliability and Life (Internals), DOE/HTGR-86-058, June 1986.

5. Haag G., 2005. Properties of ATR-2E Graphite and Property Changes Due to Fast Neutron Irradiation, Institute for Safety Research and Reactor Technology.

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