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Becht Engineering Blog

In this section of the site contributing authors submit interesting articles relating to the various services, industries and research & development efforts of Becht Engineering.

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

nuclear_plant
Bringing Order and Logic to the Evaluation ProcessThere 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 read, study, and understand.The plant engineer must understand these thousands of pages of damage mechanisms, first to take the right preventive measures, and second, when the damage occurs despite our best efforts, to correctly diagnose the remaining life of the equipment, i.e. determine its fitness-for-service, its operability.In December 2018, EPRI published “Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping” EPRI report number 3002013156, to help the plant engineer navigate through the technical and regulatory complexities of damage mechanisms and the methods for the evaluation of remaining life. This is an important step in bringing order...
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Introduction to LOCA Blowdown Loads on Reactor Internals and Fluid-Structure Interaction

Introduction to LOCA Blowdown Loads on Reactor Internals
and Fluid-Structure Interaction
Design of a Nuclear Power Plant for a LOCANuclear 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), which would challenge the plant in three ways:The pressurized cooling water, as it discharges from the break, will flash to steam. This would cause a harsh, hot, humid environment that will challenge the structures, systems, and components (SSCs) in the reactor building.The LOCA would cause the water from the broken pipe to discharge into the building instead of reaching the reactor core. This is why the RCS has redundant reactor coolant loops (RCL), and have the capability to inject additional coolant through the emergency core cooling system (ECCS). So, the ECCS is sized to make-up for the...
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