Published April 2002 | Version v1
Journal article Metadata-only

SGTR accident analysis for WWER-1000 nuclear power plant

Creators

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

Description

The author analyzes the accident of steam generator tubes rupture (SGTR) and the actions taken by operator to lessen the consequences by using thermal hydraulic code DINAMIKA-97. The calculating results are given and analysis for the results is made

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
23
Journal Issue
2
Journal Page Range
p. 51-55
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
34022718
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
CALCULATION METHODS; D CODES; HUMAN FACTORS; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR OPERATORS; RUPTURES; SAFETY ANALYSIS; STEAM GENERATORS; TUBES; WWER-5 REACTOR
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS