SYMPOSIA PAPER Published: 01 January 1988
STP33104S

Review of Pressurized-Water-Reactor-Related Thermal Shock Studies

Source

Flaw behavior trends associated with pressurized thermal shock (PTS) loading of pressurized water reactor (PWR) pressure vessels have been under investigation at Oak Ridge National Laboratory (ORNL) for approximately twelve years. During that time, eight thermal shock experiments with thick-walled steel cylinders were conducted as a part of the investigations. These experiments demonstrated, in good agreement with linear elastic fracture mechanics (LEFM), crack initiation and arrest, a series of initiation/arrest events with deep penetration of the wall, long crack jumps without significant dynamic effects at arrest, arrest in a rising stress-intensity-factor (KI) field, extensive surface extension of an initially short and shallow flaw, and warm prestressing with KI ⩽ 0. This information was used in the development of a fracture mechanics model that is being used extensively in the evaluation of the PTS issue.

Author Information

Cheverton, RD
Oak Ridge National Laboratory, Oak Ridge, TN
Iskander, SK
Computing and Telecommunications Division, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN
Ball, DG
Computing and Telecommunications Division, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN
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Details
Developed by Committee: E08
Pages: 752–766
DOI: 10.1520/STP33104S
ISBN-EB: 978-0-8031-5041-6
ISBN-13: 978-0-8031-0972-8