| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 5475119 | Annals of Nuclear Energy | 2017 | 14 Pages |
Abstract
The performed investigations elucidate the ASTECV2.0 capabilities to describe the in-vessel phase of a severe accident in a German Konvoi PWR and to assess the performance of core reflooding for slightly degraded cores. Moreover, they form the basis of future analysis on sequences with a higher contribution to the overall risk of such nuclear plant.
Keywords
MCPFOMSAMSBORCPsNPPRCSRPVECCSHPISLPISLower plenumCETaccumulatorsStation Blackoutsevere accident management guidelinescore exit temperatureHigh Pressure Injection SystemLow Pressure Injection SystemEmergency Core Cooling SystemReactor pressure vesselAccident managementSevere Accident ManagementFigure of meritnuclear power plantMain Coolant PumpSteam generator
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Ignacio Gómez-GarcÃa-Toraño, VÃctor Hugo Sánchez Espinoza, Robert Stieglitz,