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Experimental validation of calculated capture rate for nucleus involved in fuel cycle; Validation experimentale du calcul du taux de capture des noyaux intervenant dans le cycle du combustible

Abstract

The framework of this study was the evaluation of the nuclear data requirements for Actinides and Fission Products applied to current nuclear reactors as well as future applications. This last item includes extended irradiation campaigns, 100 % Mixed Oxide fuel, transmutation or even incineration. The first part of this study presents different types of integral measurements which are available for capture rate measurements, as well as the methods used for reactor core calculation route design and nuclear data library validation. The second section concerns the analysis of three specific irradiation experiments. The results have shown the extent of the current knowledge on nuclear data as well as the associated uncertainties. The third and last section shows both the coherency between all the results, and the statistical method applied for nuclear data library adjustment. A relevant application of this method has demonstrated that only specifically chosen integral experiments can be of use for the validation of nuclear data libraries. The conclusion is reached that even if co-ordinated efforts between reactor and nuclear physicists have made possible a huge improvement in the knowledge of capture cross sections of the main nuclei such as uranium and plutonium, some improvements are currently necessary for  More>>
Publication Date:
Sep 01, 1997
Product Type:
Thesis/Dissertation
Report Number:
FRCEA-TH-667
Reference Number:
SCA: 210500; 400201; PA: AIX-30:023796; EDB-99:053992; SN: 99002097691
Resource Relation:
Other Information: TH: These (CEA); PBD: Sep 1997
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 40 CHEMISTRY; ACTINIDES; AMERICIUM; CAPTURE; CROSS SECTIONS; CURIUM; FISSION PRODUCTS; FUEL CYCLE; MIXED OXIDE FUELS; NEPTUNIUM; PLUTONIUM; REACTOR CORES; REPROCESSING; SPENT FUELS; TRANSMUTATION; URANIUM
OSTI ID:
343504
Research Organizations:
CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Reacteurs; Universite de Provence, 13 - Marseille (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Other: ON: DE99623504; TRN: FR9806061023796
Availability:
INIS; OSTI as DE99623504
Submitting Site:
FRN
Size:
235 p.
Announcement Date:

Citation Formats

Benslimane-Bouland, A. Experimental validation of calculated capture rate for nucleus involved in fuel cycle; Validation experimentale du calcul du taux de capture des noyaux intervenant dans le cycle du combustible. France: N. p., 1997. Web.
Benslimane-Bouland, A. Experimental validation of calculated capture rate for nucleus involved in fuel cycle; Validation experimentale du calcul du taux de capture des noyaux intervenant dans le cycle du combustible. France.
Benslimane-Bouland, A. 1997. "Experimental validation of calculated capture rate for nucleus involved in fuel cycle; Validation experimentale du calcul du taux de capture des noyaux intervenant dans le cycle du combustible." France.
@misc{etde_343504,
title = {Experimental validation of calculated capture rate for nucleus involved in fuel cycle; Validation experimentale du calcul du taux de capture des noyaux intervenant dans le cycle du combustible}
author = {Benslimane-Bouland, A}
abstractNote = {The framework of this study was the evaluation of the nuclear data requirements for Actinides and Fission Products applied to current nuclear reactors as well as future applications. This last item includes extended irradiation campaigns, 100 % Mixed Oxide fuel, transmutation or even incineration. The first part of this study presents different types of integral measurements which are available for capture rate measurements, as well as the methods used for reactor core calculation route design and nuclear data library validation. The second section concerns the analysis of three specific irradiation experiments. The results have shown the extent of the current knowledge on nuclear data as well as the associated uncertainties. The third and last section shows both the coherency between all the results, and the statistical method applied for nuclear data library adjustment. A relevant application of this method has demonstrated that only specifically chosen integral experiments can be of use for the validation of nuclear data libraries. The conclusion is reached that even if co-ordinated efforts between reactor and nuclear physicists have made possible a huge improvement in the knowledge of capture cross sections of the main nuclei such as uranium and plutonium, some improvements are currently necessary for the minor actinides (Np, Am and Cm). Both integral and differential measurements are recommended to improve the knowledge of minor actinide cross sections. As far as integral experiments are concerned, a set of criteria to be followed during the experimental conception have been defined in order to both reduce the number of required calculation approximations, and to increase as much as possible the maximum amount of extracted information. (author)}
place = {France}
year = {1997}
month = {Sep}
}