WRAP-PWR verification studies

Technical Report · Tue Jan 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/5437830· OSTI ID:5437830

Gregory, M V; Ames, P L; Beranek, F; Kuehn, N H; Parks, P B

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.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 5437830
• Report Number(s): NUREG/CR-1681; DPST-80-4; ON: DE82015152; TRN: 82-013439
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

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