Published August 1999 | Version v1
Journal article Metadata-only

Major steam line break accident analysis

Creators

  • 1. Nuclear Power Inst. of China, Chengdu (China)

Description

During the analyses of Daya Bay Nuclear Power Plant reload, the major steam line break accident must be studied because the Doppler power feedback coefficients exceed the limiting value. The author analyzes the major steam line break accident of Daya Bay Nuclear Power Station unit 1 cycle 5 using THEMIS code and FLICA III code. The result shows that no departure from nucleate boiling occurs for any break assuming the most negative value rod cluster control assembly stuck in its full withdrawn position

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
20
Journal Issue
4
Journal Page Range
p. 326-328
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
31007256
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
DAYA BAY REACTOR; DEPARTURE NUCLEATE BOILING; F CODES; FRACTURING; NUCLEAR POWER PLANTS; SAFETY ANALYSIS; STEAM LINES; T CODES; TRANSIENTS
Descriptors DEC
BOILING; COMPUTER CODES; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; NUCLEATE BOILING; PHASE TRANSFORMATIONS; PIPELINES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS