Published June 2005 | Version v1
Journal article Metadata-only

Study on severe core damage progression induced by anticipated transients without scram and its mitigation in Qinshan NPP unit 1

Creators

  • 1. Shanghai Jiaotong Univ., Shanghai (China). Dept. of Nuclear Science and System Engineering

Description

By using a simulator based on SCDAP/RELAP5/MOD3.1 computer code, the core damage progression and the effectiveness of preventive and mitigation measures are analyzed with the anticipated transients without scram (ATWS) sequences caused by the loss of main feed water (LOFW), the loss of off-site power (LOOP) and uncontrolled rod cluster control assembly (RCCA) bank withdrawal, combined with the failure of reactor control and protection system in Qinshan Nuclear Power Plant (NPP) unit 1. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
26
Journal Issue
3
Journal Page Range
p. 209-213, 218
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
37055190
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; MELTDOWN; NUCLEAR POWER PLANTS; QINSHAN-1 REACTOR; REACTOR CORES; REMEDIAL ACTION; RISK ASSESSMENT; S CODES; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 figs., 4 tabs., 9 refs.