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3D Monte-Carlo transport calculations of whole slab reactor cores: validation of deterministic neutronic calculation routes

Abstract

This paper presents how Monte-Carlo calculations (French TRIPOLI4 poly-kinetic code with an appropriate pre-processing and post-processing software called OVNI) are used in the case of 3-dimensional heterogeneous benchmarks (slab reactor cores) to reduce model biases and enable a thorough and detailed analysis of the performances of deterministic methods and their associated data libraries with respect to key neutron parameters (reactivity, local power). Outstanding examples of application of these tools are presented regarding the new numerical methods implemented in the French lattice code APOLLO2 (advanced self-shielding models, new IDT characteristics method implemented within the discrete-ordinates flux solver model) and the JEFF3.1 nuclear data library (checked against JEF2.2 previous file). In particular we have pointed out, by performing multigroup/point-wise TRIPOLI4 (assembly and core) calculations, the efficiency (in terms of accuracy and computation time) of the new IDT method developed in APOLLO2. In addition, by performing 3-dimensional TRIPOLI4 calculations of the whole slab core (few millions of elementary volumes), the high quality of the new JEFF3.1 nuclear data files and revised evaluations (U{sup 235}, U{sup 238}, Hf) for reactivity prediction of slab cores critical experiments has been stressed. As a feedback of the whole validation process, improvements in terms of nuclear data (mainly  More>>
Authors:
Palau, J M [1] 
  1. CEA Cadarache, Service de Physique des Reacteurs et du Cycle, Lab. de Projets Nucleaires, 13 - Saint-Paul-lez-Durance (France)
Publication Date:
Jul 01, 2005
Product Type:
Conference
Report Number:
INIS-FR-09-0375
Resource Relation:
Conference: M-C 2005- International topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications, Avignon (France), 12-15 Sep 2005; Other Information: 14 refs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; A CODES; BENCHMARKS; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; T CODES; THREE-DIMENSIONAL CALCULATIONS; VALIDATION
OSTI ID:
21180685
Research Organizations:
SFEN, 75 - Paris (France)
Country of Origin:
France
Language:
English
Other Identifying Numbers:
TRN: FR0801837054888
Availability:
Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)
Submitting Site:
FRN
Size:
12 pages
Announcement Date:
Jul 17, 2009

Citation Formats

Palau, J M. 3D Monte-Carlo transport calculations of whole slab reactor cores: validation of deterministic neutronic calculation routes. France: N. p., 2005. Web.
Palau, J M. 3D Monte-Carlo transport calculations of whole slab reactor cores: validation of deterministic neutronic calculation routes. France.
Palau, J M. 2005. "3D Monte-Carlo transport calculations of whole slab reactor cores: validation of deterministic neutronic calculation routes." France.
@misc{etde_21180685,
title = {3D Monte-Carlo transport calculations of whole slab reactor cores: validation of deterministic neutronic calculation routes}
author = {Palau, J M}
abstractNote = {This paper presents how Monte-Carlo calculations (French TRIPOLI4 poly-kinetic code with an appropriate pre-processing and post-processing software called OVNI) are used in the case of 3-dimensional heterogeneous benchmarks (slab reactor cores) to reduce model biases and enable a thorough and detailed analysis of the performances of deterministic methods and their associated data libraries with respect to key neutron parameters (reactivity, local power). Outstanding examples of application of these tools are presented regarding the new numerical methods implemented in the French lattice code APOLLO2 (advanced self-shielding models, new IDT characteristics method implemented within the discrete-ordinates flux solver model) and the JEFF3.1 nuclear data library (checked against JEF2.2 previous file). In particular we have pointed out, by performing multigroup/point-wise TRIPOLI4 (assembly and core) calculations, the efficiency (in terms of accuracy and computation time) of the new IDT method developed in APOLLO2. In addition, by performing 3-dimensional TRIPOLI4 calculations of the whole slab core (few millions of elementary volumes), the high quality of the new JEFF3.1 nuclear data files and revised evaluations (U{sup 235}, U{sup 238}, Hf) for reactivity prediction of slab cores critical experiments has been stressed. As a feedback of the whole validation process, improvements in terms of nuclear data (mainly Hf capture cross-sections) and numerical methods (advanced quadrature formulas accounting validation results, validation of new self-shielding models, parallelization) are suggested to improve even more the APOLLO2-CRONOS2 standard calculation route. (author)}
place = {France}
year = {2005}
month = {Jul}
}