Conference paper Open Access

Analysis of hypothetical unprotected loss of flow in Superphénix start-up core: sensitivity to modeling details

Ponomarev Alexander; Mikityuk Konstantin


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  <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="Text">Conference paper</resourceType>
  <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="http://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">&lt;p&gt;The Superph&amp;eacute;nix (SPX) Sodium Fast Reactor (SFR) core&amp;nbsp;behaviour in a hypothetical Unprotected Loss Of Flow&amp;nbsp;(ULOF) transient scenario is simulated and the impact of the&amp;nbsp;core modelling options on the results are assessed. The&amp;nbsp;analysis has been performed using the TRACE system code&amp;nbsp;modified for the fast reactor applications using a point kinetics neutronics model and 1D multichannel&lt;br&gt;
thermal-hydraulic model. The SPX start-up core&amp;nbsp;benchmark specification was used&amp;nbsp;for calculation of neutron physics data employed as input in&amp;nbsp;the TRACE simulations. The analysis covered transient&amp;nbsp;simulation before sodium boiling onset. The influence of&amp;nbsp;control rod drive lines (CRDL) expansion reactivity effect on&amp;nbsp;the grace time before boiling was found to be significant.&amp;nbsp;Series of calculations have been performed in order to assess&amp;nbsp;sensitivity of the results to the core specification data and&amp;nbsp;modelling details in both thermal hydraulics and neutronics&amp;nbsp;inputs. In particular, two different models representing fuel&amp;nbsp;subassemblies (three-channel and multichannel) have been&amp;nbsp;employed. In addition, the influence of reactivity effects&amp;nbsp;uncertainty on transient behaviour has been assessed, as well&amp;nbsp;as sensitivity of the results to account for the spatial&amp;nbsp;distribution of reactivity effects in the core. The results of this&amp;nbsp;study serve further as a basis for the transient benchmark&amp;nbsp;exercise proposed by Ponomarev, et al., 2018 within the&amp;nbsp;framework of the Horizon-2020 ESFR-SMART project.&lt;/p&gt;</description>
  </descriptions>
  <fundingReferences>
    <fundingReference>
      <funderName>European Commission</funderName>
      <funderIdentifier funderIdentifierType="Crossref Funder ID">10.13039/501100000780</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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