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

Ponomarev Alexander; Mikityuk Konstantin

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  "description": "<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>\nthermal-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>", 
  "license": "", 
  "creator": [
      "affiliation": "PSI, Switzerland", 
      "@type": "Person", 
      "name": "Ponomarev Alexander"
      "affiliation": "PSI, Switzerland", 
      "@type": "Person", 
      "name": "Mikityuk Konstantin"
  "headline": "Analysis of hypothetical unprotected loss of flow in Superph\u00e9nix start-up core: sensitivity to modeling details", 
  "image": "", 
  "datePublished": "2019-06-29", 
  "url": "", 
  "@type": "ScholarlyArticle", 
  "@context": "", 
  "identifier": "", 
  "@id": "", 
  "workFeatured": {
    "alternateName": "ICONE27", 
    "location": "Tsukuba, Ibaraki, Japan", 
    "@type": "Event", 
    "name": "27th International Conference on Nuclear Engineering"
  "name": "Analysis of hypothetical unprotected loss of flow in Superph\u00e9nix start-up core: sensitivity to modeling details"
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