UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR

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...

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Main Authors: Abrate Nicolò, Dulla Sandra, Ravetto Piero
Format: Article
Language:English
Published: EDP Sciences 2021-01-01
Series:EPJ Web of Conferences
Subjects:
Online Access:https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_15011.pdf
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spelling doaj-dda0c2fdce754e02a3bf1ff1729c94db2021-08-02T16:01:03ZengEDP SciencesEPJ Web of Conferences2100-014X2021-01-012471501110.1051/epjconf/202124715011epjconf_physor2020_15011UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTORAbrate Nicolò0Dulla Sandra1Ravetto Piero2Politecnico di Torino, Dipartimento Energia, NEMO group Corso Duca degli AbruzziPolitecnico di Torino, Dipartimento Energia, NEMO group Corso Duca degli AbruzziPolitecnico di Torino, Dipartimento Energia, NEMO group Corso Duca degli AbruzziThe 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.https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_15011.pdflead fast reactornuclear datasamplinguncertainty propagationmulti-physics codes
collection DOAJ
language English
format Article
sources DOAJ
author Abrate Nicolò
Dulla Sandra
Ravetto Piero
spellingShingle Abrate Nicolò
Dulla Sandra
Ravetto Piero
UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
EPJ Web of Conferences
lead fast reactor
nuclear data
sampling
uncertainty propagation
multi-physics codes
author_facet Abrate Nicolò
Dulla Sandra
Ravetto Piero
author_sort Abrate Nicolò
title UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
title_short UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
title_full UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
title_fullStr UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
title_full_unstemmed UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR
title_sort uncertainty quantification in frenetic calculations of alfred lead-cooled fast reactor
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2021-01-01
description 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.
topic lead fast reactor
nuclear data
sampling
uncertainty propagation
multi-physics codes
url https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_15011.pdf
work_keys_str_mv AT abratenicolo uncertaintyquantificationinfreneticcalculationsofalfredleadcooledfastreactor
AT dullasandra uncertaintyquantificationinfreneticcalculationsofalfredleadcooledfastreactor
AT ravettopiero uncertaintyquantificationinfreneticcalculationsofalfredleadcooledfastreactor
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