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Application of RELAP4 to NUSAR accident analysis model development, description, and analysis, 1976--1977

Technical Report ·
OSTI ID:6938596
This document describes the procedure used by UNI to develop and use the RELAP4 code for analysis of the N-Reactor system during a LOCA. The code modifications required are described as are the responses to the 10CFR50 App. K requirements. Each of the models used in the analysis is described and discussed. This document is the primary reference for the LOCA analysis presented in the N-Reactor Updated Safety Analysis Report (NUSAR).
Research Organization:
United Nuclear Industries, Inc., Richland, WA (USA)
DOE Contract Number:
EY-76-C-06-1857
OSTI ID:
6938596
Report Number(s):
UNI-664
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LWGR TYPE REACTORS
MECHANICS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRESSURE GRADIENTS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTORS
TEMPERATURE GRADIENTS
WATER COOLED REACTORS