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EnglishThe paper shows the application of the most recent sensitivity techniques implemented in Serpent-2 in order to propagate the uncertainty from the nuclear data to the macroscopic, homogenised cross sections of the ALFRED reactor, which is then simulated with the multi-physics code FRENETIC. The main results are encouraging and define a possible methodology to propagate the nuclear data uncertainties to the main macroscopic parameters computed with FRENETIC, in order to perform thorough safety analyses for the ALFRED reactor.
Uncertainty quantification in frenetic calculations of ALFRED lead-cooled fast reactor / Abrate, N.; Dulla, S.; Ravetto, P.. - In: EPJ WEB OF CONFERENCES. - ISSN 2100-014X. - ELETTRONICO. - 2020-(2020), pp. 2542-2549. ((Intervento presentato al convegno 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 tenutosi a Corpus Christi and St. Catharine's Colleges, Corpus Christi and St. Catharine's Colleges, gbr nel 2020 [10.1051/epjconf/202124715011].
| Titolo: | Uncertainty quantification in frenetic calculations of ALFRED lead-cooled fast reactor | |
| Autori: | ||
| Data di pubblicazione: | 2020 | |
| Rivista: | ||
| Abstract: | The paper shows the application of the most recent sensitivity techniques implemented in Serpent-...2 in order to propagate the uncertainty from the nuclear data to the macroscopic, homogenised cross sections of the ALFRED reactor, which is then simulated with the multi-physics code FRENETIC. The main results are encouraging and define a possible methodology to propagate the nuclear data uncertainties to the main macroscopic parameters computed with FRENETIC, in order to perform thorough safety analyses for the ALFRED reactor. | |
| Appare nelle tipologie: | 4.1 Contributo in Atti di convegno |
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