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PWR hot leg natural circulation modeling with MELCOR code

Abstract

Previous MELCOR and SCDAP/RELAP5 nodalizations for simulating the counter-current, natural circulation behavior of vapor flow within the RCS hot legs and SG U-tubes when core damage progress can not be applied to the steady state and water-filled conditions during the initial period of accident progression because of the artificially high loss coefficients in the hot legs and SG U-tubes which were chosen from results of COMMIX calculation and the Westinghouse natural circulation experiments in a 1/7-scale facility for simulating steam natural circulation behavior in the vessel and circulation modeling which can be used both for the liquid flow condition at steady state and for the vapor flow condition at the later period of in-vessel core damage. For this, the drag forces resulting from the momentum exchange effects between the two vapor streams in the hot leg was modeled as a pressure drop by pump model. This hot leg natural circulation modeling of MELCOR was able to reproduce similar mass flow rates with those predicted by previous models. 6 refs., 2 figs. (Author)
Authors:
Park, Jae Hong; Lee, Jong In [1] 
  1. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
Publication Date:
Dec 31, 1997
Product Type:
Conference
Report Number:
ETDE/KR-99732628; CONF-9710296-
Reference Number:
SCA: 210200; 220200; 220504; PA: KR-99:000281; EDB-99:035046; SN: 99002059908
Resource Relation:
Conference: Korean Nuclear Society autumn meeting, Taegu (Korea, Republic of), 24-25 Oct 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the korean nuclear society autumn meeting vol I, October 24-25, 1997 Taegu, Korea; PB: 797 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; PWR TYPE REACTORS; NATURAL CONVECTION; M CODES; VAPORS; REACTOR COOLING SYSTEMS; STEAM GENERATORS; SIMULATION; SCALE MODELS
OSTI ID:
324067
Research Organizations:
Korean Nuclear Society, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE99732628; TRN: KR9900281
Availability:
OSTI as DE99732628
Submitting Site:
KR
Size:
pp. 772-777
Announcement Date:

Citation Formats

Park, Jae Hong, and Lee, Jong In. PWR hot leg natural circulation modeling with MELCOR code. Korea, Republic of: N. p., 1997. Web.
Park, Jae Hong, & Lee, Jong In. PWR hot leg natural circulation modeling with MELCOR code. Korea, Republic of.
Park, Jae Hong, and Lee, Jong In. 1997. "PWR hot leg natural circulation modeling with MELCOR code." Korea, Republic of.
@misc{etde_324067,
title = {PWR hot leg natural circulation modeling with MELCOR code}
author = {Park, Jae Hong, and Lee, Jong In}
abstractNote = {Previous MELCOR and SCDAP/RELAP5 nodalizations for simulating the counter-current, natural circulation behavior of vapor flow within the RCS hot legs and SG U-tubes when core damage progress can not be applied to the steady state and water-filled conditions during the initial period of accident progression because of the artificially high loss coefficients in the hot legs and SG U-tubes which were chosen from results of COMMIX calculation and the Westinghouse natural circulation experiments in a 1/7-scale facility for simulating steam natural circulation behavior in the vessel and circulation modeling which can be used both for the liquid flow condition at steady state and for the vapor flow condition at the later period of in-vessel core damage. For this, the drag forces resulting from the momentum exchange effects between the two vapor streams in the hot leg was modeled as a pressure drop by pump model. This hot leg natural circulation modeling of MELCOR was able to reproduce similar mass flow rates with those predicted by previous models. 6 refs., 2 figs. (Author)}
place = {Korea, Republic of}
year = {1997}
month = {Dec}
}