June 29, 2019 Conference paper Open Access

Ponomarev Alexander; Mikityuk Konstantin

MARC21 XML Export

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    <subfield code="a">Analysis of hypothetical unprotected loss of flow in Superphénix start-up core: sensitivity to modeling details</subfield>
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    <subfield code="a">&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;</subfield>
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