Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Pressurizer component studies with RELAP4/MOD6. [PWR]

Technical Report ·
OSTI ID:6471517
The results are presented of the independent assessment studies of the RELAP4/MOD6 computer code for the pressurizer component during the blowdown phase of the loss-of-coolant accident. RELAP4 pressurizer component models were driven with measured boundary conditions from Semiscale and LOFT blowdown experiments, and the results were compared to test data. The sensitivity of the calculated results to model nodalization, code options, and uncertainty in the boundary conditions was determined.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6471517
Report Number(s):
CAAP-TR-78-028
Country of Publication:
United States
Language:
English

Similar Records

Steam generator component studies with RELAP4/MOD6. [PWR]
Technical Report · Sat Jul 01 00:00:00 EDT 1978 · OSTI ID:6471482
Comparisons of RELAP4/MOD6 with core blowdown data
Technical Report · Mon May 01 00:00:00 EDT 1978 · OSTI ID:6494149
Comparisons of RELAP4/MOD6 with Semiscale blowdown data. [PWR]
Technical Report · Sat Jul 01 00:00:00 EDT 1978 · OSTI ID:6541702

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
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
LIQUID FLOW
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE GRADIENTS
PRESSURIZERS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS