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Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite

Abstract

The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and life-time. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then, neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimized. (author)
Authors:
Publication Date:
Dec 01, 2001
Product Type:
Thesis/Dissertation
Report Number:
FRCEA-TH-835
Resource Relation:
Other Information: TH: These physique des reacteurs; 156 refs; PBD: Dec 2001
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCURACY; ADJOINT FLUX; BOLTZMANN EQUATION; COMPUTERIZED SIMULATION; DATA COVARIANCES; MATERIAL BUCKLING; NEUTRON IMPORTANCE FUNCTION; OPTIMIZATION; PERTURBATION THEORY; PWR TYPE REACTORS; SENSITIVITY ANALYSIS; SHIP PROPULSION REACTORS
OSTI ID:
20267144
Research Organizations:
CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d'Etudes des Reacteurs; Universite Blaise Pascal, Clermont-Ferrand II, (CNRS), 63 - Aubiere (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR0202448034153
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
237 pages
Announcement Date:
Aug 30, 2002

Citation Formats

Bernard, D. Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite. France: N. p., 2001. Web.
Bernard, D. Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite. France.
Bernard, D. 2001. "Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite." France.
@misc{etde_20267144,
title = {Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite}
author = {Bernard, D}
abstractNote = {The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and life-time. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then, neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimized. (author)}
place = {France}
year = {2001}
month = {Dec}
}