16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 290 / 295Document ID.No.UKEPR-0002-162 Issue 04SECTION 16.2.2.4 - TABLE 9[Ref]W Schmidt. Mass- and Energy Release into the Containment due to Ex-Vessel MeltStabilization. NGPS4/2005/en/1061 Revision B. AREVA NP. June 2007. (E)SECTION 16.2.2.4 - FIGURE 1[Ref]M Fischer. System CMSS: CMSS System Description. NEPS-G/2008/en/1116.AREVA NP. (E)SECTION 16.2.2.4 - FIGURES 2 TO 4[Ref]M Nie, M Fischer. Analysis of the melt retention in the reactor pit for various releasesequences. NGPS4/2003/en/0003. AREVA NP. July 2003. (E)SECTION 16.2.2.4 - FIGURE 5[Ref][Ref]P Gandrille. EPR RF002. Severe Accidents. Dedicated Reactor Coolant SystemDepressurisation. Functional requirements. NFEPD DC 0091. Framatome ANP.January 2003. (E)M Nie, M Fischer. Analysis of the melt retention in the reactor pit for various releasesequences. NGPS4/2003/en/0003. AREVA NP. July 2003. (E)SECTION 16.2.2.4 – FIGURES 8 TO 11[Ref]M Nie, M Fischer. Analysis of the melt retention in the reactor pit for various releasesequences. NGPS4/2003/en/0003. AREVA NP. July 2003. (E)SECTION 16.2.2.4 - FIGURES 12 TO 16[Ref]W Schmidt. Mass and Energy Release into the Containment due to Ex-Vessel MeltStabilization. NGPS4/2005/en/1061 Revision B. AREVA NP. June 2007. (E)SECTION 16.2.2.4 – FIGURE 17[Ref]R Wittmaack. EPR corium spreading analysis with the CORFLOW computer code.KWU NA-T/1998/E077 Revision A. AREVA NP Erlangen. August 1998. (E)SECTION 16.2.2.4 - FIGURES 18 AND 19[Ref]M Fischer. Long-term Melt Stabilization as Part of the Severe Accident MitigationStrategy of the European Pressurized Water Reactor. ICAPP05-5001, Seoul, Korea,15-19 May 2005. (E)