Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams-Reference-Cited by-同舟云学术

Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

Published:1999-10 Issue:12 Volume:76 Page:813-823
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:

Jhung Myung Jo,Park Youn Won,Jang Changheui

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference9 articles.

1. PTS integrity study in Japan;Mishima;International Journal of Pressure Vessels and Piping,1994

2. Sievers J, Schulz H. Final Report on the International Comparative Assessment Study of Pressurized Thermal Shock in Reactor Pressure Vessels. NEA/CSNI/R(99)3, OECD/NEA/CSNI PWG-3, May 1999.

3. Pressure vessel integrity under pressurized thermal shock conditions;Stahlkopf;Nuclear Engineering and Design,1984

4. Deterministic structural and fracture mechanics analyses of reactor pressure vessel for pressurized thermal shock;Jhung;Structural Engineering and Mechanics,1999

5. ASME. Rules for inservice inspection of nuclear power plant components. ASME Boiler and Pressure Vessel Code, Section XI, 1998.

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