An updated probabilistic fracture mechanics methodology for application to pressurized thermal shock-Reference-Cited by-同舟云学术

An updated probabilistic fracture mechanics methodology for application to pressurized thermal shock

Published:2001-02 Issue:2-3 Volume:78 Page:155-163
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Dickson Terry L,Malik Shah N.M

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference24 articles.

1. Code of Federal Regulations, Title 10, Part 50, Section 50.61 and Appendix G.

2. US Nuclear Regulatory Commission. Regulatory Guide 1.154. Format and content of plant-specific pressurized thermal shock safety analysis reports for pressurized water reactors, 1987.

3. Dickson TL. FAVOR: a fracture analysis code for nuclear reactor pressure vessels. Release 9401. ORNL/NRC/LTR 94-1, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, February, 1994.

4. Dickson TL. An overview of FAVOR: a fracture analysis code for nuclear reactor pressure vessels. Transactions of the 13th International Conference on Structural Mechanics in Reactor Technology (SMiRT 13), Porto Alegre, Brazil, August, vol. IV, 1995. p. 701–6.

5. Reactor vessel integrity database, NUREG-1511, US Nuclear Regulatory Commission, December, 1994, NUREG-1511, Suppl 1, October, 1996; RVID Version 2.0, August, 1997.

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