Published April 2, 2000 | Version v1
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SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor

Description

The SCDAP/RELAP5 code is being developed at the Idaho National Engineering and Environmental Laboratory under the primary sponsorship of the U.S. Nuclear Regulatory Commission (NRC) to provide best-estimate transient simulations of light water reactor coolant systems during severe accidents. This paper describes the modeling approach used in the SCDAP/RELAP5 code to calculate fluid heat transfer and flow losses through porous debris that has accumulated in the vessel lower head and core regions during the latter stages of a severe accident. The implementation of heat transfer and flow loss correlations into the code is discussed, and calculations performed to assess the validity of the modeling approach are described. The different modes of heat transfer in porous debris include: (1) forced convection to liquid, (2) forced convection to gas, (3) nucleate boiling, (4) transition boiling, (5) film boiling, and (6) transition from film boiling to convection to vapor. The correlations for flow losses in porous debris include frictional and form losses. The correlations for flow losses were integrated into the momentum equations in the RELAP5 part of the code. Since RELAP5 is a very general non-homogeneous non-equilibrium thermal-hydraulics code, the resulting modeling methodology is applicable to a wide range of debris thermal-hydraulic conditions. Assessment of the SCDAP/RELAP5 debris bed thermal-hydraulic models included comparisons with experimental measurements and other models available in the open literature. The assessment calculations, described in the paper, showed that SCDAP/RELAP5 is capable of calculating the heat transfer and flow losses occurring in porous debris regions that may develop in a light water reactor during a severe accident

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00758106; PURL: https://www.osti.gov/servlets/purl/758106-rSaPuK/webviewable/

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
INEEL/CON--99-01325

Conference

Title
International Conference on Nuclear Engineering
Acronym
ICONE 8
Dates
2-6 Apr 2000
Place
Baltimore, MD (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
31051290
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORIUM; FLUID FLOW; HEAT TRANSFER; POROUS MATERIALS; PRESSURE VESSELS; R CODES; REACTOR ACCIDENTS; S CODES; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; MATERIALS; REACTORS

Optional Information

Contract/Grant/Project number
AC07-99ID13727
Funding organization
US Department of Energy (United States)