Published February 1986 | Version v1
Report Metadata-only

Application of TBL results to BWR plants

Creators

  • 1. Energy Research Lab., Hitachi Ltd., Ibaraki, Japan

Description

Parallel channel models for large break loss-of-coolant accidents (LOCAs) have been developed, based on experimental results of countercurrent gas-liquid flow in parallel vertical channels simulating a BWR core. The models were composed of flow distribution and flow pattern transition models, which calculated the steam flow rates from the lower plenum into each region of the core and the numbers of countercurrent flow and cocurrent up-flow bundles, respectively. These models were applied to the transient analysis program, SAFER, and verified by a TBL (Two Bundle Loop) large break test analysis

Additional details

Publishing Information

Imprint Title
Thirteenth water reactor safety research information meeting: proceedings. Volume 5
Journal Page Range
p. 77-100.
Report number
NUREG/CP--0072-Vol.5

Conference

Title
13. water reactor safety research information meeting.
Dates
22-25 Oct 1985.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18002554
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; ECCS; FLOW MODELS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PIPES; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RUPTURES; S CODES; TESTING; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS