Operability And Fitness-for-Service (FFS) Of ASME Equipment In Nuclear Power Plants

Bringing Order and Logic to the Evaluation Process There is a multitude of documents and reports that describe the damage mechanisms of ASME pressure equipment (vessels, pumps, valves, piping, and tanks, and their supports) in nuclear power plants. Thousands of pages published by EPRI, the NRC, ASME, NACE, research laboratories, utilities, contractors, and others, to […]

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Introduction to LOCA Blowdown Loads on Reactor Internals and Fluid-Structure Interaction

Design of a Nuclear Power Plant for a LOCA Nuclear power plants are designed with the capability to safely shut-down following a number of hypothetical accident scenarios. One of those accidents is the rupture of a pipe in the reactor coolant system (RCS). Such a rupture would result in a loss of coolant accident (LOCA), […]

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