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Title: Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]

Abstract

This paper describes a RELAP4/MOD7 simulation of West Germany's Kraftwerk Union (KWU) Primary Coolant Loop (PKL) refill/reflood experiment K9A. RELAP4/MOD7, a best-estimate computer program for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This study was the first major simulation using RELAP4/MOD7 since its release by the Idaho National Engineering Laboratory (INEL). The PKL facility is a reduced scale (1:134) representation of a typical West German four-loop 1300 MW pressurized water reactor (PWR). A prototypical scale of the total volume to power ratio was maintained. The test facility was designed specifically for an experiment simulating the refill/reflood phase of a Loss-of-Coolant Accident (LOCA).

Authors:
; ;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
5462659
Report Number(s):
CONF-811101-23
ON: DE82007638; TRN: 82-008581
DOE Contract Number:  
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: Winter annual meeting of the ASME Technology and Society Division, Washington, DC, USA, 15 Nov 1981
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; HEAT TRANSFER; HYDRAULICS; TEST FACILITIES; PWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; MOCKUP; REACTOR SAFETY; ACCIDENTS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Hsu, M.T., Davis, C.B., and Behling, S.R. Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]. United States: N. p., 1981. Web.
Hsu, M.T., Davis, C.B., & Behling, S.R. Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]. United States.
Hsu, M.T., Davis, C.B., and Behling, S.R. Sun . "Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]". United States. https://www.osti.gov/servlets/purl/5462659.
@article{osti_5462659,
title = {Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]},
author = {Hsu, M.T. and Davis, C.B. and Behling, S.R.},
abstractNote = {This paper describes a RELAP4/MOD7 simulation of West Germany's Kraftwerk Union (KWU) Primary Coolant Loop (PKL) refill/reflood experiment K9A. RELAP4/MOD7, a best-estimate computer program for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This study was the first major simulation using RELAP4/MOD7 since its release by the Idaho National Engineering Laboratory (INEL). The PKL facility is a reduced scale (1:134) representation of a typical West German four-loop 1300 MW pressurized water reactor (PWR). A prototypical scale of the total volume to power ratio was maintained. The test facility was designed specifically for an experiment simulating the refill/reflood phase of a Loss-of-Coolant Accident (LOCA).},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {11}
}

Conference:
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