Published 1986 | Version v1
Book Metadata-only

Assessment of the SAFER program for core spray line break LOCA with data from the two bundle loop (TBL)

Creators

  • 1. Hitachi Ltd., Tokyo (Japan)

Description

The response of the boiling water reactor (BWR) under the postulated loss of coolant accidents (LOCA) was simulated in the Two Bundle Loop (TBL) facility. The TBL was constructed to simulate a jet-pump type BWR/5 - 251 plant with 764 fuel bundles. This paper presents the results of a core spray line break test. The results were analyzed with the SAFER program. SAFER is a one-dimensional thermal-hydraulic program for realistic analysis of BWR LOCA. SAFER prediction agreed well with the experiment, and showed slightly higher peak cladding temperature (PCT). Futhermore, TBL results were analyzed with TRAC, which is a best estimate program with three-dimensional, two-fluid non-equilibrium models. TRAC prediction also agreed with the experiment, and identified conservatism of SAFER models. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Soc. of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
Imprint Pagination
1191 p.
Journal Page Range
p. 2/204-2/209.

Conference

Title
2. international topical meeting on nuclear power plant thermal hydraulics and operations.
Dates
15-17 Apr 1986.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
18061695
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; CORE SPRAY SYSTEMS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYDRAULICS; JETS; LOSS OF COOLANT; PUMPS; REACTOR SAFETY EXPERIMENTS; S CODES; SIMULATION; T CODES; THERMODYNAMICS; TIME DEPENDENCE
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; EVALUATION; FUEL ASSEMBLIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS