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

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SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 289 / 295Document ID.No.UKEPR-0002-162 Issue 042.4.1.5.2. Modelling approach2.4.1.5.2.2. Melt flooding and quenching[Ref][Ref][Ref][Ref][Ref]M T Farmer, et al. MACE Test M3b, Data Report. MACE-TR-D13, Vol. 1/2. ArgonneNat. Lab. November 1997. (E)M T Farmer, et al. MACE Test M1B, Data Report. MACE-TR-D6. Argonne Nat. Lab.September 1992. (E)M T Farmer, et al. MACE Test M4, Data Report. MACE-TR-D16. Argonne Nat. Lab.August 1999. (E)B R Sehgal, T N Dinh, R R Nourgaliev, M J Konovalikhin, V A Bui. “Assessment of CoreMelt Spreading in EPR Melt Retention Device”. Sehgal Associates Inc., October 15,1998. (E)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 - TABLE 1[Ref]M Nie, M Fischer. Parametric examination of the sacrificial concrete layer thickness inthe spreading compartment. NGPS4/2004/en/0185 Revision A. TR04/166. AREVA NP.(E)SECTION 16.2.2.4 – TABLE 2[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 – TABLE 3[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 – TABLE 5[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 - TABLES 6 TO 8[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)
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)
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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