Constitutive modeling and finite element procedure development for stress analysis of prismatic high temperature gas cooled reactor graphite core components-Reference-Cited by-同舟云学术

Constitutive modeling and finite element procedure development for stress analysis of prismatic high temperature gas cooled reactor graphite core components

Published:2013-07 Issue: Volume:260 Page:145-154
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mohanty Subhasish,Majumdar Saurindranath,Srinivasan Makuteswara

Funder

U.S. Department of Energy

U.S. Nuclear Regulatory Commission

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

Reference17 articles.

1. Bratton, R.L., 2009. Modeling mechanical behavior of a prismatic replaceable reflector block. INL/EXT-09-15868, Idaho National Laboratory, Idaho Falls, ID.

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

3. Graphite Design Handbook, 1988. DOE-HTGR-88111, General Atomics Company, CA.

4. Harper, P.G., 1980. User guide to BERSAFE phase III for reactor graphite. RD/B/N4797.

5. IAEA-TECHDOC, 1988. High temperature gas cooled reactor technology development. IAEA- TECHDOC-TECHDOC988.

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