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

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

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SUB-CHAPTER : <strong>16.2</strong>PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 291 / 295Document ID.No.UKEPR-0002-162 Issue 04SECTION <strong>16.2</strong>.2.4 – FIGURE 19[Ref]M Fischer. The Core Melt Stabilization Concept of the EPR and its ExperimentalValidation. ICONE 14-89088, Miami FL, USA, 19-23 July 2006. (E)SECTION <strong>16.2</strong>.2.4 - FIGURES 20 AND 21[Ref]M Nie, M Fischer. “<strong>Analysis</strong> of the melt retention in the reactor pit for various releasesequences”. NGPS4/2003/en/0003. AREVA NP. (E)2.5. CONTAINMENT PRESSURE AND CONTAINMENT TEMPERATURE2.5.1. Methods and basic assumptions for pressure and temperaturecalculations2.5.1.3. Determination of flow rates[Ref]M Fischer, M Nie. Updating of mass and energy release into the containment based onthe latest R&D results. NGPS4/2003/en/0059 Revision B. AREVA NP. January 2004.(E)2.5.2. Containment data2.5.2.2. Boundary conditions[Ref]K-G Petzold. EPR Basic Containment Model for the "Lumped Parameter" codeCOCOSYS including the Combustible Gas Control System. NEPS-G/2007/en/0035.AREVA NP. December 2007. (E)SECTION <strong>16.2</strong>.2.5 - TABLES[Ref][Ref][Ref]K-G Petzold. EPR Basic Containment Model for the "Lumped Parameter" codeCOCOSYS including the Combustible Gas Control System. NEPS-G/2007/en/0035.AREVA NP. December 2007. (E)M Nie, K-G Petzold. Main data for severe accident analyses. FANPNGES2/2002/en/0006 Revision D. AREVA Erlangen. January 2004. (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 <strong>16.2</strong>.2.5 - FIGURES[Ref]M Nie, et al. Loads on Containment Civil Structures resulting from <strong>Severe</strong> <strong>Accident</strong>s.NGPS4/2005/en/1067 Revision E. AREVA NP. June 2008. (E)

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