publication . Conference object . Article . Other literature type . 2019

ANALYSIS OF HYPOTHETICAL UNPROTECTED LOSS OF FLOW IN SUPERPHÉNIX START-UP CORE: SENSITIVITY TO MODELING DETAILS

Ponomarev Alexander; Mikityuk Konstantin;
Open Access
  • Published: 29 Jun 2019
Abstract
The Superphénix (SPX) Sodium Fast Reactor (SFR) core behaviour in a hypothetical Unprotected Loss Of Flow (ULOF) transient scenario is simulated and the impact of the core modelling options on the results are assessed. The analysis has been performed using the TRACE system code modified for the fast reactor applications using a point kinetics neutronics model and 1D multichannel<br> thermal-hydraulic model. The SPX start-up core benchmark specification was used for calculation of neutron physics data employed as input in the TRACE simulations. The analysis covered transient simulation before sodium boiling onset. The influence of control rod drive lines (CRDL) e...
Subjects
free text keywords: Environmental science, Flow (psychology), Nuclear engineering, Start up
Funded by
EC| ESFR-SMART
Project
ESFR-SMART
European Sodium Fast Reactor Safety Measures Assessment and Research Tools
  • Funder: European Commission (EC)
  • Project Code: 754501
  • Funding stream: H2020 | RIA
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Conference object . 2019
Provider: ZENODO
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Other literature type . 2019
Provider: Datacite
Zenodo
Other literature type . 2019
Provider: Datacite
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publication . Conference object . Article . Other literature type . 2019

ANALYSIS OF HYPOTHETICAL UNPROTECTED LOSS OF FLOW IN SUPERPHÉNIX START-UP CORE: SENSITIVITY TO MODELING DETAILS

Ponomarev Alexander; Mikityuk Konstantin;