Published November 1985 | Version v1
Journal article Metadata-only

Effect of interphase friction on void fraction prediction

Creators

  • 1. Babcock and Wilcox Co., Lynchburg, VA

Description

The RELAP5/MOD1 transient thermal-hydraulic system analysis code has been developed to evaluate pressurized water reactor behavior during accident conditions. Benchmark cases have shown RELAP5/MOD1 to differ from the measured void distribution in certain relevant tests. In an attempt to achieve better agreement, the Wallis annular interphase drag correlation was replaced by the Bharathan-Wallis correlation in the Babcock and Wilcox version of RELAP5/MOD1 (REDBL5). The simulation of two Christensen's subcooled boiling tests using REDBL5 shows better agreement between the measured and calculated void distributions

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
50
Series
Trans. Am. Nucl. Soc.
Journal Page Range
626-628
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society winter meeting.
Dates
10-15 Nov 1985.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17078789
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; TRANSIENTS; VOID FRACTION
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-851115--.