Open Access
ND 2007
Article Number 236
Number of page(s) 4
Section Fission applications
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07423

Using various point wise and multi-group cross section libraries in MORET criticality calculations

Joachim Miss1, Olivier Jacquet2, Franck Bernard1, Isabelle Duhamel1, Stéphane Evo1 and Marc Leclere1

1  Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Fontenay-aux-Roses, France
2  Independent consultant, Salignac, France

Published online: 21 May 2008

Most modern criticality safety Monte Carlo codes have reached a good level of achievement concerning the implemented simulation algorithms. Discrepancies observed on final results (for example performed by different teams with different codes and data) are mainly due to the used nuclear data. Therefore, knowing and controlling the way of processing nuclear data libraries used by these codes is nowadays crucial. Recent MORET code (developed by IRSN) improvements have focused on the development of a prototypic continuous energy version. Indeed, so far, the cross sections used by the MORET code are read from external multi-group libraries. It has been then decided to plan new developments in MORET 5 to control the whole criticality calculation process, from the reading of nuclear data to the Monte Carlo simulation itself. The new features related to this new version will allow performing criticality calculations either with a multi-group or a continuous energy treatment. The goal of this paper is to present the main topics needed to ensure proper development of a continuous energy version of MORET, and the results concerning the use of various multi-group cross sections libraries in MORET.

© CEA 2008