Conference paper Open Access
Ponomarev Alexander; Mikityuk Konstantin
<?xml version='1.0' encoding='utf-8'?> <resource xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns="http://datacite.org/schema/kernel-4" xsi:schemaLocation="http://datacite.org/schema/kernel-4 http://schema.datacite.org/meta/kernel-4.1/metadata.xsd"> <identifier identifierType="DOI">10.5281/zenodo.3262074</identifier> <creators> <creator> <creatorName>Ponomarev Alexander</creatorName> <affiliation>PSI, Switzerland</affiliation> </creator> <creator> <creatorName>Mikityuk Konstantin</creatorName> <affiliation>PSI, Switzerland</affiliation> </creator> </creators> <titles> <title>Analysis of hypothetical unprotected loss of flow in Superphénix start-up core: sensitivity to modeling details</title> </titles> <publisher>Zenodo</publisher> <publicationYear>2019</publicationYear> <dates> <date dateType="Issued">2019-06-29</date> </dates> <resourceType resourceTypeGeneral="ConferencePaper"/> <alternateIdentifiers> <alternateIdentifier alternateIdentifierType="url">https://zenodo.org/record/3262074</alternateIdentifier> </alternateIdentifiers> <relatedIdentifiers> <relatedIdentifier relatedIdentifierType="DOI" relationType="IsVersionOf">10.5281/zenodo.3262073</relatedIdentifier> </relatedIdentifiers> <rightsList> <rights rightsURI="https://creativecommons.org/licenses/by/4.0/legalcode">Creative Commons Attribution 4.0 International</rights> <rights rightsURI="info:eu-repo/semantics/openAccess">Open Access</rights> </rightsList> <descriptions> <description descriptionType="Abstract"><p>The Superph&eacute;nix (SPX) Sodium Fast Reactor (SFR) core&nbsp;behaviour in a hypothetical Unprotected Loss Of Flow&nbsp;(ULOF) transient scenario is simulated and the impact of the&nbsp;core modelling options on the results are assessed. The&nbsp;analysis has been performed using the TRACE system code&nbsp;modified for the fast reactor applications using a point kinetics neutronics model and 1D multichannel<br> thermal-hydraulic model. The SPX start-up core&nbsp;benchmark specification was used&nbsp;for calculation of neutron physics data employed as input in&nbsp;the TRACE simulations. The analysis covered transient&nbsp;simulation before sodium boiling onset. The influence of&nbsp;control rod drive lines (CRDL) expansion reactivity effect on&nbsp;the grace time before boiling was found to be significant.&nbsp;Series of calculations have been performed in order to assess&nbsp;sensitivity of the results to the core specification data and&nbsp;modelling details in both thermal hydraulics and neutronics&nbsp;inputs. In particular, two different models representing fuel&nbsp;subassemblies (three-channel and multichannel) have been&nbsp;employed. In addition, the influence of reactivity effects&nbsp;uncertainty on transient behaviour has been assessed, as well&nbsp;as sensitivity of the results to account for the spatial&nbsp;distribution of reactivity effects in the core. The results of this&nbsp;study serve further as a basis for the transient benchmark&nbsp;exercise proposed by Ponomarev, et al., 2018 within the&nbsp;framework of the Horizon-2020 ESFR-SMART project.</p></description> </descriptions> <fundingReferences> <fundingReference> <funderName>European Commission</funderName> <funderIdentifier funderIdentifierType="Crossref Funder ID">10.13039/100010661</funderIdentifier> <awardNumber awardURI="info:eu-repo/grantAgreement/EC/H2020/754501/">754501</awardNumber> <awardTitle>European Sodium Fast Reactor Safety Measures Assessment and Research Tools</awardTitle> </fundingReference> </fundingReferences> </resource>
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