Published August 2003 | Version v1
Journal article Metadata-only

The development of a safety analysis code--SAC-PREARS

Creators

  • 1. Nanhua University, Hunan (China)
  • 2. Xi'an Jiaotong University, Xi'an (China)

Description

The basic mathematic and physical model has been established and the results have been validated by comparing with those of MISAP and the general code TRAC-PF1. The results show that SAC-PREARS can effectively compute and analyze the steady state and transient thermal-hydraulic characteristics of the residual-heat-removal system of NHR

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
24
Journal Issue
4
Journal Page Range
p. 384-386
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
34084223
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT REMOVAL; COMPARATIVE EVALUATIONS; MATHEMATICAL MODELS; NATURAL CONVECTION; PROCESS HEAT REACTORS; PROGRAMMING; REACTOR SAFETY; S CODES; SAFETY ANALYSIS; VALIDATION
Descriptors DEC
COMPUTER CODES; CONVECTION; ENERGY TRANSFER; EVALUATION; HEAT TRANSFER; MASS TRANSFER; REACTORS; REMOVAL; SAFETY; TESTING