The restraining effect of austenitic cladding on the extension of a three-dimensional crack into the wall of a water-cooled nuclear reactor pressure vessel during a hypothetical overcooling accident-Reference-Cited by-同舟云学术

The restraining effect of austenitic cladding on the extension of a three-dimensional crack into the wall of a water-cooled nuclear reactor pressure vessel during a hypothetical overcooling accident

Published:1984-03 Issue:1 Volume:78 Page:79-84
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Smith E.

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

Reference5 articles.

1. ASME Boiler and Pressure Vessel Code,1975

2. ORNL/NUREG/TM-31;Cheverton,1976

3. The effect of austenitic cladding on the extension of an under-clad crack into the wall of a water-cooled nuclear reactor pressure vessel during a hypothetical loss-of-coolant accident;Smith,1983

4. Flaw evaluation procedures: Background and application of ASME Section XI,1978

5. The stress analysis of cracks handbook;Tada,1973

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1. Edwin Smith. 28 July 1931 — 4 July 2010;Biographical Memoirs of Fellows of the Royal Society;2017-01

2. Determination of residual stress and strain fields caused by cladding and tempering of reactor pressure vessels;International Journal of Pressure Vessels and Piping;2000-10

3. TRANSIENT THERMAL STRESSES IN A CLADDED SEMI-INFINITE MEDIUM CONTAINING AN UNDERCLAD CRACK;Journal of Thermal Stresses;1995-05

4. Thermal-shock experiments with flawed clad cylinders;Nuclear Engineering and Design;1990-11

5. Trends in the evaluation of the structural integrity of RPVs;Nuclear Engineering and Design;1989-09