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Uncertainty Analysis of Kinetic Parameters for Design, Operation and Safety Analysis of SFRs

Jun 28, 2017, 5:50 PM
1h 10m
Yekaterinburg

Yekaterinburg

POSTER Track 6. Test Reactors, Experiments and Modeling and Simulations Poster Session 2

Speaker

Ivan A. Kodeli (Institut Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia)

Description

Uncertainty Analysis of Kinetic Parameters for Design, Operation and Safety Analysis of SFRs I.-A. Kodeli Institut Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia G. Rimpault, P. Dufay, Y. Peneliau, J. Tommasi French Alternative and Atomic Energy Commission (CEA), Cadarache Center, 13108 Saint-Paul-lez-Durance, France E. Fridman Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, D-01328 Dresden W. Zwermann, A. Aures Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), Garching, Germany E. Ivanov IRSN, 92262 Fontenay-aux-Roses, France K. Ivanov North Carolina State University, Raleigh, NC 27695, USA Y. Nakahara, T. Ivanova, J. Gulliford OECD, NEA, 92100 Boulogne-Billancourt, France An OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) has been initiated in 2015 under the NSC/WPRS/EGUAM with the objective to study the uncertainties in different stages of Sodium Fast Reactors. Best-estimate codes and data together with an evaluation of the uncertainties are required for that purpose, which challenges existing calculation methods. Neutronic feedback coefficients as well as the kinetic parameters are being calculated for transient analyses. Experimental evidence in support of the studies is also being developed. The use of the Iterated Fission Probability method in the Monte Carlo codes such as Tripoli4® Serpent-2 and MCNP-5 gives reference values for calculating βeff. Deterministic codes like ERANOS and PARTISN/SUSD3D are also used for nuclear data sensitivity analysis and uncertainty propagation. The derived values are validated against experiments and their uncertainties. A vast series of experiments has been selected and analysed leading to recommendations on the tools, procedures and data to be used for beta-eff calculating of the benchmarks including uncertainties.

Country/Int. Organization

Institut Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia

Primary author

Ivan A. Kodeli (Institut Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia)

Co-authors

A. Aures (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), Garching, Germany) E. Fridman (Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, D-01328 Dresden) E. Ivanov (IRSN, 92262 Fontenay-aux-Roses, France) G. Rimpault (French Alternative and Atomic Energy Commission (CEA), Cadarache Center, 13108 Saint-Paul-lez-Durance, France) J. Gulliford (OECD, NEA, 92100 Boulogne-Billancourt, France) J. Tommasi (French Alternative and Atomic Energy Commission (CEA), Cadarache Center, 13108 Saint-Paul-lez-Durance, France) K. Ivanov (North Carolina State University, Raleigh, NC 27695, USA) P. Dufay (French Alternative and Atomic Energy Commission (CEA), Cadarache Center, 13108 Saint-Paul-lez-Durance, France) T. Ivanova (OECD, NEA, 92100 Boulogne-Billancourt, France) W. Zwermann (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), Garching, Germany) Y. Nakahara (OECD, NEA, 92100 Boulogne-Billancourt, France) Y. Peneliau (French Alternative and Atomic Energy Commission (CEA), Cadarache Center, 13108 Saint-Paul-lez-Durance, France)

Presentation materials