| Issue |
EPJ Web Conf.
Volume 146, 2017
ND 2016: International Conference on Nuclear Data for Science and Technology
|
|
|---|---|---|
| Article Number | 09021 | |
| Number of page(s) | 4 | |
| Section | Nuclear Data for Applications | |
| DOI | https://doi.org/10.1051/epjconf/201714609021 | |
| Published online | 13 September 2017 | |
https://doi.org/10.1051/epjconf/201714609021
Decay heat uncertainty quantification of MYRRHA
1 SCK·CEN, Boeretang 200, 2400 Mol, Belgium
2 ULB, Université Libre de Bruxelles, Avenue Franklin Roosevelt 50, 1050 Brussels, Belgium
3 AREVA GmbH, Dept. Radiology & Criticality, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany
a e-mail: lfiorito@sckcen.be
b e-mail: oliver.buss@areva.com
Published online: 13 September 2017
MYRRHA is a lead-bismuth cooled MOX-fueled accelerator driven system (ADS) currently in the design phase at SCK·CEN in Belgium. The correct evaluation of the decay heat and of its uncertainty level is very important for the safety demonstration of the reactor. In the first part of this work we assessed the decay heat released by the MYRRHA core using the ALEPH-2 burnup code. The second part of the study focused on the nuclear data uncertainty and covariance propagation to the MYRRHA decay heat. Radioactive decay data, independent fission yield and cross section uncertainties/covariances were propagated using two nuclear data sampling codes, namely NUDUNA and SANDY. According to the results, 238U cross sections and fission yield data are the largest contributors to the MYRRHA decay heat uncertainty. The calculated uncertainty values are deemed acceptable from the safety point of view as they are well within the available regulatory limits.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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