
doi: 10.2172/5437830
A modular computational system known as the Water Reactor Analysis Package - Evaluation Model (WRAP-EM) was developed for the Nuclear Regulatory Commission (NRC) to interpret and evaluate reactor vendor EM methods and computed results. A subset of the system (WRAP-PWR-EM) provides the computational tools to perform a complete analysis of loss-of-coolant accidents (LOCA's) in pressurized water reactors (PWR's). A set of calculations modeling experimental tests in the Semiscale and LOFT facilities, and calculations of a large break in a typical four-loop Westinghouse PWR plant have verified that the WRAP-PWR-EM system is functioning as intended.
Loss Of Coolant, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Reactor Cores, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 530, Reactor Accidents, Fuel Rods, Fuel Elements, Reactor Components, Light-Water Moderated, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Pwr Type Reactors, Heat Transfer, Reactors, Energy Transfer, Accidents, Blowdown, Water Cooled Reactors, 210200 -- Power Reactors, Fuel Assemblies, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
Loss Of Coolant, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Reactor Cores, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 530, Reactor Accidents, Fuel Rods, Fuel Elements, Reactor Components, Light-Water Moderated, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Pwr Type Reactors, Heat Transfer, Reactors, Energy Transfer, Accidents, Blowdown, Water Cooled Reactors, 210200 -- Power Reactors, Fuel Assemblies, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
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