Published February 1994 | Version v1
Journal article Metadata-only

Modified RELAP4/MOD7 code and large break loss of water accident analysis

Creators

  • 1. Beijing Inst. of Nuclear Engineering (China)

Description

The RELAP4/MOD7 is a large transient thermohydraulic calculation code which is licensed by American NRC for engineering examining. The calculation result of large break loss of water accident using modified RELAP4/MOD7 code is agreeable to the foreign calculation result of same kind nuclear plant

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
15
Journal Issue
1
Journal Page Range
p. 7-11.
ISSN
0258-0926
CODEN
HDGOE6

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
26031425
Subject category
S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
LOSS OF COOLANT; MODIFICATIONS; R CODES; REWETTING; SAFETY ANALYSIS; SIMULATION; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; REACTOR ACCIDENTS