Published September 1989 | Version v1
Journal article Metadata-only

The application of TRAC-PF1 to the analysis of large break LOCA

Creators

  • 1. Qinghua Univ., Beijing, BJ (China). Dept. of Engineering Physics

Description

A brief description of the features of TRAC-PF1 in connection with the analysis of a large break LOCA is given. The model used for the analysis of large break LOCA by TRAC-PF1 for the nuclear steam supply system of Qinshan Nuclear Power Plant is described. The results of steady-state initialization calculation, basic assumptions, sequence of events, and some curves of transient processes are presented. The results obtained are discussed, and the key input data for obtaining the results of the analysis of large break LOCA of Qinshan Nuclear Power Plant are pointed out. A method for analyzing large break LOCA using TRAC-PF1 is recommended

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
23
Journal Issue
5
Series
At. Energy Sci. Technol.
Journal Page Range
75-80
ISSN
1000-6931
CODEN
YKJIE

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
21054629
Subject category
S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; EVALUATION; FUNCTIONAL MODELS; LOSS OF COOLANT; PRESSURE VESSELS; QINSHAN REACTOR; REACTOR CORES; STEADY-STATE CONDITIONS; STEAM GENERATORS; T CODES
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; CONTAINERS; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS