Integrity of PWR pressure vessels during overcooling transients

Journal Article · · Nucl. Saf.; (United States)

OSTI ID:5870237

Cheverton, R D ^[1]; Iskander, S K; Whitman, G D

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1. Oak Ridge National Lab., TN

A class of postulated transients, referred to as overcooling transients, can subject the pressure vessel in a pressurized-water reactor to severe thermal shock while the pressure is substantial. As a result of such transients, vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. A state-of-the-art fracture-mechanics model was developed to evaluate this problem. Results indicate that some vessels may have a potential for failure in a few years if subjected to the type of transient experienced at Rancho Seco in 1978. The possibility that the calculational model may be excessively conservative is under investigation.

• OSTI ID: 5870237
• Journal Information: Nucl. Saf.; (United States), Journal Name: Nucl. Saf.; (United States) Vol. 24:2; ISSN NUSAA
• Country of Publication: United States
• Language: English

Related Subjects

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220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
FRACTURE MECHANICS
MATHEMATICAL MODELS
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PRESSURE VESSELS
PWR TYPE REACTORS
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THERMAL SHOCK
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS