The BWR Loss-of-Coolant Accident Analysis Capability of the Wrap-Em System

Technical Report · Sun Apr 01 04:00:00 EST 1979

DOI:https://doi.org/10.2172/6068988· OSTI ID:6068988

Buckner, M. R. ^[1]; Beckmeyer, R. R. ^[1]; Gregory, M. V. ^[1]; Reed, R. L. ^[1]; Winn, W. G. ^[1]

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1. Savannah River National Laboratory (SRNL), Aiken, SC (United States)

The modular computational system known as the Water Reactor Analysis Package (WRAP) has been extended to provide the computational tools required to perform a complete analysis of LOCAs in BWRs. The new system is known as the WRAP-EM (Evaluation Model) system and will be used by NRC in interpreting and evaluating reactor vendor EM methods and computed results. The system for BWR-EM analysis is comprised of several computer codes which have been developed to analyze a particular phase of a LOCA. These codes include GAPCON for calculation of initial fuel conditions, WRAP (the previously developed SRL analog of RELAP4/MOD5) for analysis of the system blowdown, NORCOOL for analysis of the reflood phase, and MOXY for the calculation of the fuel assembly hot plane temperature. In addition, a BWR steady-state initialization procedure has been developed to provide the initial operating state of the reactor system. The BWR-EM system is operational and is currently being evaluated to determine the adequacy and consistency of the physical models employed for EM analysis.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States). Savannah River Ecology Laboratory (SREL)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: EY-76-C-09-0001
• OSTI ID: 6068988
• Report Number(s): NUREG/CR--0713; DPST-NUREG--78-2
• Country of Publication: United States
• Language: English

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