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A global approach to the physics validation of simulation codes for future nuclear systems

Funded under: FP7-EURATOM


This paper presents a global approach to the validation of the parameters that enter into the neutronics simulation tools for advanced fast reactors with the objective to reduce the uncertainties associated to crucial design parameters. This global approach makes use of sensitivity/uncertainty methods; statistical data adjustments; integral experiment selection, analysis and "representativity" quantification with respect to a reference system; scientifically based cross-section covariance data and appropriate methods for their use in multigroup calculations. This global approach has been applied to the uncertainty reduction on the criticality of the Advanced Burner Reactor (both metal and oxide core versions) presently investigated in the frame of the GNEP initiative. The results obtained are very encouraging and allow to indicate some possible improvements of the ENDF/B-VII data file.

Additional information

Authors: PALMIOTTI G, Idaho National Laboratory, Idaho Falls (US);SALVATORES M, Idaho National Laboratory, Idaho Falls (US);HIRUTA H, Idaho National Laboratory, Idaho Falls (US);ALIBERTI G, Argonne National Laboratory, Argonne (US);MCKNIGHT R, Argonne National Laboratory, Argonne (US);YANG W S, Argonne National Laboratory, Argonne (US);OBLOZINSKY P, Brookhaven National Laboratory, Upton (US)
Bibliographic Reference: An article published in: Annals of Nuclear Energy, Volume 36, Issue 3, 2009, pp. 355-361
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Record Number: 200910367 / Last updated on: 2009-09-22
Original language: en
Available languages: en