Published August 2001 | Version v1
Journal article Metadata-only

Transient property simulating and dealing of small-break loss-of-coolant accident in nuclear power plant

Creators

  • 1. Naval Univ. of Engineering, Wuhan (China)

Description

Nuclear power plant operation analysis code is designed and developed, on the base of nonhomogeneous and nonequilibrium model for the two-phase flow, by solving a fast partially implicit numerical scheme, and is used to analyze transient property of a small-break loss-of-coolant accident in nuclear power unit. Method to deal the accident are proposed

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
22
Journal Issue
4
Journal Page Range
p. 337-341
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
33014622
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CRITICAL FLOW; DATA PROCESSING; FINITE DIFFERENCE METHOD; HUMAN FACTORS; LOSS OF COOLANT; MATHEMATICAL MODELS; POWER REACTORS; PRESSURIZERS; REACTOR SAFETY; SAFETY ANALYSIS; SIMULATION; TIME DEPENDENCE; TRANSIENTS; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; FLUID FLOW; ITERATIVE METHODS; NUMERICAL SOLUTION; PROCESSING; REACTOR ACCIDENTS; REACTORS; SAFETY