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Title: SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor

Abstract

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-hydraulicmore » 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.« less

Authors:
;
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
758106
Report Number(s):
INEEL/CON-99-01325
TRN: US0003760
DOE Contract Number:  
AC07-99ID13727
Resource Type:
Conference
Resource Relation:
Conference: 8th International Conference on Nuclear Engineering (ICONE-8), Baltimore, MD (US), 04/02/2000--04/07/2000; Other Information: PBD: 2 Apr 2000
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; S CODES; R CODES; WATER COOLED REACTORS; REACTOR ACCIDENTS; HEAT TRANSFER; FLUID FLOW; POROUS MATERIALS; CORIUM; PRESSURE VESSELS; SCDAP/RELAP5; REACTOR COOLANT SYSTEMS; SEVERE ACCIDENTS; FLUID HEAT TRANSFER; FLOW LOSSES; POROUS DEBRIS; VESSEL LOWER HEAD; MODELING APPROACH; THERMAL-HYDRAULIC

Citation Formats

Harvego, E A, and Siefken, L J. SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor. United States: N. p., 2000. Web.
Harvego, E A, & Siefken, L J. SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor. United States.
Harvego, E A, and Siefken, L J. Sun . "SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor". United States. https://www.osti.gov/servlets/purl/758106.
@article{osti_758106,
title = {SCDAP/RELAP5 modeling of fluid heat transfer and flow losses through porous debris in a light water reactor},
author = {Harvego, E A and Siefken, L J},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {4}
}

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