| Issue |
EPJ Nuclear Sci. Technol.
Volume 6, 2020
|
|
|---|---|---|
| Article Number | 8 | |
| Number of page(s) | 9 | |
| DOI | https://doi.org/10.1051/epjn/2020003 | |
| Published online | 08 April 2020 | |
https://doi.org/10.1051/epjn/2020003
Regular Article
Uncertainty propagation based on correlated sampling technique for nuclear data applications
1
Laboratory for Reactor Physics and Systems behaviour (LRS), Ecole Polytechnique Fédérale de Lausanne (EPFL), 1015 Lausanne, Switzerland
2
Laboratory for Reactor Physics and Thermal Hydraulics (LRT), Paul Scherrer Institut (PSI), 5232 Villigen, Switzerland
3
Nuclear Energy and Safety Research Division (NES), Paul Scherrer Institut (PSI), 5232 Villigen, Switzerland
* e-mail: laureau.axel@gmail.com
Received:
2
September
2019
Received in final form:
15
November
2019
Accepted:
16
January
2020
Published online: 8 April 2020
A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.
© A. Laureau et al., published by EDP Sciences, 2020
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (https://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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