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Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies

Abstract

The growing interest in safety problems had led physicists to try to increase their knowledge of the neutron leakage phenomenon, both by calculation and by experiment. The flux calculation in a heterogeneous assembly is frequently performed by collision probability method. On the contrary, neutron leakage is calculated for a flux-weighted homogenized assembly, which is a good approximation for a non-voided assembly (PWR in normal conditions). In a LOCA situation, the assembly may contain void zones, and this model for leakage calculation may become insufficient. We propose here a new theoretical model, taking into account the effect of heterogeneity of the assembly on neutron leakage, and which was implemented as TIBERE procedure in the multigroup transport assembly code APPOLO-2. One of the advantages of this new model is to allow a perfectly consistent definition of cell reaction and cell leakage rates used in the equivalence procedure. As well as this theoretical work was made, an experimental program concerning this phenomenon was performed as a part of EPICURE experiment. Comparisons of experimental and calculational results point out better agreement of the new model with the measurements.
Authors:
Benoist, P; Petrovic, I; [1]  Mondot, J [2] 
  1. CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
  2. CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Reacteurs
Publication Date:
Jun 01, 1993
Product Type:
Conference
Report Number:
CEA-CONF-11278; CONF-930404-
Reference Number:
SCA: 210200; 990200; PA: AIX-24:042496; SN: 93000990812
Resource Relation:
Conference: International topical meeting on mathematical methods and supercomputing in nuclear applications (M&C+SNA `93),Karlsruhe (Germany),19-23 Apr 1993; Other Information: PBD: 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; LOSS OF COOLANT; VOID COEFFICIENT; NEUTRON LEAKAGE; A CODES; PWR TYPE REACTORS; HETEROGENEOUS REACTOR CORES; 210200; 990200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; MATHEMATICS AND COMPUTERS
OSTI ID:
10154581
Research Organizations:
CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
Country of Origin:
France
Language:
English
Other Identifying Numbers:
Other: ON: DE93626259; TRN: FR9302245042496
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
[15] p.
Announcement Date:
Jul 06, 2005

Citation Formats

Benoist, P, Petrovic, I, and Mondot, J. Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies. France: N. p., 1993. Web.
Benoist, P, Petrovic, I, & Mondot, J. Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies. France.
Benoist, P, Petrovic, I, and Mondot, J. 1993. "Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies." France.
@misc{etde_10154581,
title = {Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies}
author = {Benoist, P, Petrovic, I, and Mondot, J}
abstractNote = {The growing interest in safety problems had led physicists to try to increase their knowledge of the neutron leakage phenomenon, both by calculation and by experiment. The flux calculation in a heterogeneous assembly is frequently performed by collision probability method. On the contrary, neutron leakage is calculated for a flux-weighted homogenized assembly, which is a good approximation for a non-voided assembly (PWR in normal conditions). In a LOCA situation, the assembly may contain void zones, and this model for leakage calculation may become insufficient. We propose here a new theoretical model, taking into account the effect of heterogeneity of the assembly on neutron leakage, and which was implemented as TIBERE procedure in the multigroup transport assembly code APPOLO-2. One of the advantages of this new model is to allow a perfectly consistent definition of cell reaction and cell leakage rates used in the equivalence procedure. As well as this theoretical work was made, an experimental program concerning this phenomenon was performed as a part of EPICURE experiment. Comparisons of experimental and calculational results point out better agreement of the new model with the measurements.}
place = {France}
year = {1993}
month = {Jun}
}