Abstract
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.
Original language | English |
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Title of host publication | EPJ Web of Conferences |
Subtitle of host publication | ND 2016: International conference on nuclear data for science and technology |
Pages | 1-4 |
Number of pages | 4 |
Volume | 146 |
Edition | 2017 |
DOIs | |
State | Published - 18 Sep 2017 |
Event | 2016 - ND: International Conference on Nuclear Data for Science and Technology - Concert gebouw en Oud Sint Jan Hospitaal, Bruges Duration: 11 Sep 2016 → 16 Sep 2016 http://www.nd2016.eu/ |
Publication series
Name | EPJ Web of Conferences |
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Publisher | EDP Sciences |
ISSN (Print) | 2100-014X |
Conference
Conference | 2016 - ND |
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Abbreviated title | ND2016 |
Country/Territory | Belgium |
City | Bruges |
Period | 2016-09-11 → 2016-09-16 |
Internet address |
ASJC Scopus subject areas
- Nuclear Energy and Engineering