The Viability of the K<sub>Ia</sub> Procedure for Predicting the Arrest of a Deep Crack During a Hypothetical Thermal Shock Event Involving a Water-Cooled Nuclear Reactor Pressure Vessel

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1989-08-22T00:00:00+00:00

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F - LWR Pressure Components
F01 - Pressurized Thermal Shock
SMiRT 10 - Anaheim, CA, USA. August 22-27, 1989

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IASMiRT

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