BWR loss-of-coolant accident analysis capability of the WRAP-EM system
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 51 p.
- Report number
- NUREG/CR--0713
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10480028
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE GRADIENTS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- DPST-NUREG--78-2.