Published 1983 | Version v1
Book Metadata-only

Analytical study of BWR upper plenum behavior under LOCA by TRAC-BD1

Creators

  • 1. Nippon Atomic Industry Group Co., Ltd., NAIG Nuclear Research Lab.

Description

This paper describes analytical results of BWR upper plenum behavior under LOCA using the TRAC-BD1 code and comparisons with ESTA (Eighteen Degrees Sector Test Apparatus) results. TRAC-BD1 is a best estimate system code and features a three dimensional treatment of the BWR pressure vessel and one dimensional treatment of fuel bundles and pipings. ESTA is the LOCA refill-reflood test facility which mocks up an 18 degrees sector of the BWR with full height from jet pump bottom to standpipe top. Analyses of ESTA saturated CCFL test and subcooled CCFL breakdown tests are performed by using the TRAC-BD1 code with the special emphasis on multidimensional nonequilibrium two phase flow behavior in the upper plenum associated with CCFL and CCFL breakdown at the upper tie plate. It is confirmed that TRAC-BD1 can predict not only the multi-bundle saturated CCFL characteristics but the effect of spray temperature on CCFL breakdown qualitatively

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-89448-110-X
Imprint Title
Thermal hydraulics of nuclear reactors
Journal Page Range
p. 713-717.

Conference

Title
2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
Dates
11-13 Jan 1983.
Place
Santa Barbara, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17089441
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANALYTICAL SOLUTION; BWR TYPE REACTORS; CORE SPRAY SYSTEMS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYDRAULICS; JETS; LOSS OF COOLANT; MOCKUP; ONE-DIMENSIONAL CALCULATIONS; PIPES; PRESSURE VESSELS; PUMPS; QUENCHING; REACTOR CORES; T CODES; TESTING; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; FUEL ASSEMBLIES; HEAT TREATMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS