Published 1986 | Version v1
Book Metadata-only

Qualification of CORECOOL using parametric spray heat transfer tests by various axial power distribution heated bundle

Creators

  • 1. Toshiba Corp., Kawasaki, Kanagawa (Japan)

Description

Parametric spray heat transfer tests have been conducted under simulated spray cooling conditions of BWR during a LOCA using full scale electrically heated bundles with cosine, bottom and top peaked power distributions. The test parameters are spray flow rate, system pressure, bundle power and initial rod temperature. Using these test data, verification of mechanistic spray heat transfer evaluation code CORECOOL has been performed. It is verified that CORECOOL predicts well the maximum temperature transient in the rod bundle as well as average temperature transient under wide range of spray cooling conditions regardless of axial power distribution. (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. 1/50-1/56.

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
18042199
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; C CODES; CORE SPRAY SYSTEMS; HEAT TRANSFER; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS