Reactor cooling systems thermal-hydraulic assessment of the ASTEC V1.3 code in support of the French IRSN PSA-2 on the 1300 MWe PWRs |
| |
Authors: | Nicolas Tregoures,Marc Philippot,Laurent Foucher,Gaé tan Guillard,Joë lle Fleurot |
| |
Affiliation: | Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Centre d’Etudes Nucléaires de Cadarache BP3, F-13115 Saint-Paul-lez-Durance Cedex, France |
| |
Abstract: | The French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) is performing a level 2 Probabilistic Safety Assessment (PSA-2) on the French 1300 MWe PWRs. This PSA-2 study is relying on the ASTEC integral computer code, jointly developed by IRSN and GRS (Germany). In order to assess the reliability and the quality of physical results of the ASTEC V1.3 code as well as the PWR 1300 MWe reference input deck, a wide-ranging series of comparisons with the French best-estimate thermal-hydraulic code CATHARE 2 V2.5 has been performed on 14 different severe-accident scenarios. The present paper details 4 out of the 14 studied scenarios: a 12-in. cold leg Loss of Coolant Accident (LOCA), a 2-tube Steam Generator Tube Rupture (SGTR), a 12-in. Steam Line Break (SLB) and a total Loss of Feed Water scenario (LFW). The thermal-hydraulic behavior of the primary and secondary circuits is thoroughly investigated and compared to the CATAHRE 2 V2.5 results. The ASTEC results of the core degradation phase are also presented. Overall, the thermal-hydraulic behavior given by the ASTEC V1.3 is in very good agreement with the CATHARE 2 V2.5 results. |
| |
Keywords: | AFWS, Auxiliary Feed Water System ASDV, Atmospheric Steam Dump Valve ASTEC, Accident Term Source Evaluation Code CSS, Containment Spray System GRS, Gesellschaft fü r Anlagen und ReaktorSicherheit IRSN, Institut de Radioprotection et de Sû reté Nuclé aire LOCA, Loss of Coolant Accident LPSI, Low Pressure Safety Injection LWR, Light Water Reactor MFWS, Main Feed Water System MPSI, Middle Pressure Safety Injection PRV, Pressurizer Relief Valve PSA-2, Probabilistic Safety Assessment-level 2 PWR, Pressurized Water Reactor RCS, Reactor Cooling System RWST, Refueling Water Storage Tank SARNET, Severe Accident Research NETwork SBO, Station Black Out SGRV, Steam Generator Relief Valve SGTR, Steam Generator Tube Rupture SI, Safety Injection system SLB, Steam Line Break |
本文献已被 ScienceDirect 等数据库收录! |
|