User's guide for the PWR LOCA analysis capability of the WRAP-EM system
The Water Reactor Analysis Package (WRAP) has been expanded to provide the capability to analyze loss-of-coolant accidents (LOCAs) in both pressurized water reactors (PWRs) and boiling water reactors (BWRs) by using evaluation models (EMs). The input specifications for modules in the WRAP-EM system are presented in this document along with the JOSHUA input templates. This document, along with the WRAP user's guide, provides a step-by-step procedure for setting up a PWR data base for the WRAP-EM system. 12 refs.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 5435309
- Report Number(s):
- NUREG/CR-1679; DPST-80-2; ON: TI85015950
- Country of Publication:
- United States
- Language:
- English
Similar Records
User's Guide for the BWR LOCA Analysis Capability of the WRAP-EM System
WRAP-BWR-EM system development and application
WRAP-PWR verification studies
Technical Report
·
Sat Mar 31 23:00:00 EST 1979
·
OSTI ID:6168806
WRAP-BWR-EM system development and application
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5800213
WRAP-PWR verification studies
Technical Report
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5437830
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
COMPUTERIZED SIMULATION
CREEP
DEFORMATION
ENERGY TRANSFER
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICAL PROPERTIES
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
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
COMPUTERIZED SIMULATION
CREEP
DEFORMATION
ENERGY TRANSFER
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICAL PROPERTIES
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS