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 : 291 / 295Document ID.No.UKEPR-0002-162 Issue 04SECTION 16.2.2.4 – 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 16.2.2.4 - FIGURES 20 AND 21[Ref]M Nie, M Fischer. “Analysis 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 16.2.2.5 - 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 16.2.2.5 - FIGURES[Ref]M Nie, et al. Loads on Containment Civil Structures resulting from Severe Accidents.NGPS4/2005/en/1067 Revision E. AREVA NP. June 2008. (E)
SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 292 / 295Document ID.No.UKEPR-0002-162 Issue 043. RADIOLOGICAL CONSEQUENCES OF CORE-MELTSEQUENCES3.1. SAFETY REQUIREMENTS3.1.2. Radiological objectives[Ref][Ref][Ref][Ref][Ref]Principles for Intervention for Protection of the Public in a Radiological Emergency, Areport by a task group of Committee 4 of ICRP, adopted by the ICRP in November1992, Oxford, New York, Seoul, Tokyo. ICRP Publication 63. ICRP. 1993. (E)European Council. Council Regulation (Euratom) 3954/87 Specifying Maximum Valuesfor Radioactivity in Foodstuffs and Animal Feeds in the Event of a Nuclear Accident orOther Radiological Emergency. Official Journal of the European Community No.L371/11, 1987, amended by Council Regulation 2218/89. Official Journal of theEuropean Community No. L211/1. 1989. (E)National Radiological Protection Board. Emergency reference levels of dose for earlycountermeasures to protect the public. Doc NRPB 1(4). 1990. (E)European Council. Council Regulation (Euratom) 3954/87 Specifying Maximum Valuesfor Radioactivity in Foodstuffs and Animal Feeds in the Event of a Nuclear Accident orOther Radiological Emergency. Official Journal of the European Community No.L371/11, 1987, amended by Council Regulation 2218/89. Official Journal of theEuropean Community No. L211/1, 1989. (E)Food and Environment Protection Act 1985. HMSO. 1985. (E)3.2. REFERENCE SOURCE TERM3.2.1. Core Inventory[Ref]C Gauld, O W Hermann, R M Westfall. ORIGEN-S: Scale System Module to calculatefuel depletion, actinide transmutation, fission product build-up and decay, andassociated radiation source terms.NUREG/CR-200, ORNL/TM-2005/39 Version 6 Volume. II, Section. F7.Oak Ridge National Laboratory. 2002. (E)3.2.3. In-containment aerosol behaviour[Ref]J L Droulas. Physical assumptions for calculating the source term under severeaccident conditions. ENTTH/0000277 Revision B1. EDF. December 2010. (E)ENTTH/0000277 Revision B1 is the English translation of ENTTH/0000277 Revision B.
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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