Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue

Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue [electronic resource]

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We present statistical analyses of pressurized water reactor (PWR) primary coolant leak events caused by thermal fatigue, and discuss their safety significance. Our worldwide data contain 13 leak events (through-wall cracking) in 3509 reactor-years, all in stainless steel piping with diameter less t...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Idaho National Engineering and Environmental Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1999.
Subjects:
Failure Mode Analysis.
Primary Coolant Circuits.
Crack Propagation.
Data Analysis.
Pwr Type Reactors.
Reliability.
Reactor Safety.
Stainless Steels.
Thermal Fatigue.
Specific Nuclear Reactors And Associated Plants.
General Studies Of Nuclear Reactors.
Materials Science.

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Call Number: E 1.99:INEEL/CON-99-00320
E 1.99:INEEL/CON-99-00320 Available

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