Conference paper Open Access

3-D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET code

Henry, Romain; Seubert, Armin


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  <identifier identifierType="DOI">10.5281/zenodo.3541503</identifier>
  <creators>
    <creator>
      <creatorName>Henry, Romain</creatorName>
      <givenName>Romain</givenName>
      <familyName>Henry</familyName>
      <affiliation>GRS</affiliation>
    </creator>
    <creator>
      <creatorName>Seubert, Armin</creatorName>
      <givenName>Armin</givenName>
      <familyName>Seubert</familyName>
      <affiliation>GRS</affiliation>
    </creator>
  </creators>
  <titles>
    <title>3-D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET code</title>
  </titles>
  <publisher>Zenodo</publisher>
  <publicationYear>2019</publicationYear>
  <dates>
    <date dateType="Issued">2019-11-14</date>
  </dates>
  <resourceType resourceTypeGeneral="Text">Conference paper</resourceType>
  <alternateIdentifiers>
    <alternateIdentifier alternateIdentifierType="url">https://zenodo.org/record/3541503</alternateIdentifier>
  </alternateIdentifiers>
  <relatedIdentifiers>
    <relatedIdentifier relatedIdentifierType="DOI" relationType="IsVersionOf">10.5281/zenodo.3541502</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">&lt;p&gt;Most of the safety criteria for Sodium cooled Fast Reactors (SFR) are local core parameters. Thus, application of 3-D neutron kinetic and thermal-hydraulic coupled codes including detailed modelling of core expansion effects is mandatory for best estimate evaluations of safety margins. A recently published benchmark related to Superph&amp;eacute;nix offers the opportunity to validate codes and methods for SFR safety assessment. This requires the generation of few-group cross-sections. Since whole core Serpent Monte Carlo models for production of such cross-section libraries would be computationally costly (and the standard 2-D approach may introduce unnecessary large approximations), 3-D models of each sub-assembly type in infinite radial lattice configurations have been created with Serpent. To simplify the handling of temperature dependent geometric changes, a pre-processor for generation of temperature driven expansion of geometry and material densities has been developed and implemented in the GRS core simulator KMACS. These cross-sections are then used to evaluate effective multiplication factors and 3-D distributions of power density using PARCS for different core configurations. The results are compared with the reference calculation and with experimental data provided with the benchmark. In the next step, a simple ATHLET parallel channel open core model has been developed for coupled PARCS/ATHLET first transient test calculations. This paper describes in detail the models and techniques used for the generation of the few-group parameterized cross section libraries, the PARCS model and the ATHLET open core model and first transient test calculations.&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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