The effect of nuclear data on the MCNPX modeling of moderator level variations in the CROCUS critical facility

A detailed MCNPX (version 2.4.0) model of the CROCUS zero-power critical facility was used to investigate the effect of nuclear data on the analysis of reactivity perturbations caused by variations in the moderator level. The analysis was performed using the ENDF/B-VI (Release 0), ENDF/B-V, JEF-2.2 and JENDL-3.2 cross-section libraries, and compared with experimental values derived from period measurements. The results of this study demonstrate that predictions of the reactivity effects of moderator-level variations are largely independent of the nuclear data evaluation even when the associated keff values vary significantly.


Published in:
Journal of Nuclear Science and Technology, 40, 6, 429-432
Year:
2003
Publisher:
Atomic Energy Society of Japan
Keywords:
Note:
Paul Scherrer Institute, CH-5232 Villigen PSI, Switzerland
Laboratories:




 Record created 2010-09-17, last modified 2018-09-13


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