Application of RELAP4 to NUSAR accident analysis revised manifold and pressure tube break analysis

Technical Report · Mon Jun 26 04:00:00 EDT 1978

OSTI ID:6697907

Madsen, D R

This document describes the RELAP4 reanalysis of the hot and cold-leg manifold break and pressure tube break cases. The models used are described as well as the results. A justification for use of a correction factor for the Moody critical flow model is presented. A discharge coefficient sensitivity study and a CV-5 valve response study are also presented for the cold-leg manifold analysis.

• Research Organization: United Nuclear Industries, Inc., Richland, WA (USA)
• DOE Contract Number: EY-76-C-06-1857
• OSTI ID: 6697907
• Report Number(s): UNI-664(Add.1)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LWGR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRESSURE GRADIENTS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS