WRAP-PWR verification studies
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 (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 5437830
- Report Number(s):
- NUREG/CR-1681; DPST-80-4; ON: DE82015152
- Country of Publication:
- United States
- Language:
- English
Similar Records
PWR loss-of-coolant accident analysis capability of the WRAP-EM system
User's guide for the PWR LOCA analysis capability of the WRAP-EM system
WRAP-PWR-EM system development and applications
Technical Report
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:5320730
User's guide for the PWR LOCA analysis capability of the WRAP-EM system
Technical Report
·
Thu Jan 31 23:00:00 EST 1980
·
OSTI ID:5435309
WRAP-PWR-EM system development and applications
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5779331
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS