DocumentCode
271037
Title
Analysis of the AMMON Experimental Program in the EOLE Facility Supporting the Qualification of the JHR Neutron and Photon Tools
Author
Vaglio-Gaudard, C. ; Colombier, A.C. ; Hudelot, J.P. ; Leray, O. ; Lemaire, Martin ; Sergeyeva, V. ; Di Salvo, J. ; Gruel, A. ; SireÌta, P.
Author_Institution
DEN, CEA, St. Paul-lez-Durance, France
Volume
61
Issue
4
fYear
2014
fDate
Aug. 2014
Firstpage
2246
Lastpage
2253
Abstract
The first criticality of the international Jules Horowitz Material Testing Reactor (JHR) now under construction at CEA Cadarache, is planned by the end of the decade. In order to perform all the design and safety studies, the specific neutron and photon calculation tools, HORUS3D/N&P, dedicated to JHR simulation, were developed. This development follows the Verification & Validation-Uncertainty Quantification process; within this framework, the validation step aims at quantifying all the biases and associated uncertainties of the HORUS3D/N&P calculations. These biases originate from both the nuclear data and the calculation scheme, for JHR calculations at beginning of life or during depletion (in particular for the JHR core at equilibrium). This paper focuses on the quantification of the biases due to nuclear data and the associated uncertainties. A new experimental program, named AMMON, was conducted between 2010 and 2013 to provide experimental data for this quantification. A large part of the measurements has been analyzed using the Monte Carlo TRIPOLI-4 code and the JEFF3.1.1 and EPDL97 data libraries relative to neutron/photon transport and photon emission. The calculation biases, that rely on the discrepancies between Calculation and Experiment during the AMMON analysis, were transposed from AMMON to JHR. The synthesis of the present analysis is very satisfactory. The calculation biases remain limited. In addition, thanks to a very good control of the experimental uncertainties during measurements, it is shown that the a priori uncertainties due to nuclear data for parameters at JHR´s beginning of life were reduced up to a factor of 2.
Keywords
Monte Carlo methods; fission reactor design; fission reactor fuel; fission reactor safety; neutron transport theory; photon transport theory; AMMON experimental program; EOLE facility; EPDL97 data library; JEFF3.1.1 data library; JHR neutron tools; JHR photon tools; JHR simulation; Monte Carlo TRIPOLI-4 code; associated uncertainties; international Jules Horowitz Material Testing Reactor; neutron-photon transport emission; photon emission; validation-uncertainty quantification process; Assembly; Fuels; Inductors; Monte Carlo methods; Neutrons; Photonics; Uncertainty; EOLE experimental facility; JHR; Monte Carlo; neutronics; qualification;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2014.2306440
Filename
6819470
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