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 : 277 / 295Document ID.No.UKEPR-0002-162 Issue 04[Ref][Ref][Ref][Ref][Ref][Ref]Current Severe Accident Research Facilities and Projects. NEA/CSNI/R(2004)6. OECD.2004. (E)J M Bonnet et al. KROTOS FCI Experimental Programme at CEA Cadarache: NewFeatures and Status. Popes’ Palace Conference Centre, Avignon, France. October 2-6,2005.N I Kolev. Verification of IVA5 Computer Code for Melt-Water Interaction Analysis. 7 thInternational Conference on Nuclear Engineering, ICONE-7359, Tokyo, Japan. 1999.(E)T G Theofanous, W W Yuen, K Freeman and X Chen. The verification basis of theESPROSE.m code. Nuclear Engineering and Design Volume 189, 103-138. Elsevier.1999. (E)T G Theofanous, W W Yuen and S Angilini. The verification basis of the PM-ALPHAcode. Nuclear Engineering and Design Volume 189, 59-102. Elsevier. 1999. (E)Identification of Relevant Conditions and Experiments for Fuel-Coolant Interactions inNuclear Power Plants. NEA/CSNI/R(2004)7. OECD NEA. 2004. (E)1.3.1.2. Ex-vessel steam explosion[Ref][Ref][Ref]M T Farmer, et al. MACE Test M3b, Data Report. MACE-TR-D13, Volume. 1/2. ArgonneNat. Lab. November 1997. (E)M T Farmer, et al. MACE Test M4, Data Report. MACE-TR-D16. Argonne Nat. Lab.August 1999. (E)M T Farmer, S Basu. A Summary of Findings from the Melt Coolability and ConcreteInteractions (MCCI) Program. Proceedings of ICAPP 2007, Nice, France, paper 7544.May 2007. (E)1.3.2 Recriticality1.3.2.1 In-Vessel Recriticality[Ref] J.F. Briefmeister. MCNP – A General Monte Carlo N-Particle Transport Code. V. 4C,LANL-13709-M. (E)[Ref]G. Ducros. "An overview of the VERCORS experimental programme”. InternationalVERCORS Seminar, Greoux les bains, France. October 2007. (E)1.3.2.1.2 Assessment of the Potential for Recriticality during Phase 2[Ref] Staff Reports to the President’s Commission on the Accident at Three Mile Island. NRC.(E)
SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 278 / 295Document ID.No.UKEPR-0002-162 Issue 042. ANALYSIS OF CORE MELT SEQUENCES2.1. IN-VESSEL ACCIDENT PROGRESSION AND SELECTION OFRELEVANT SCENARIOS2.1.1. Analysis of Core Melt Scenarios2.1.1.2. Analyses of Core Melt Scenarios2.1.1.2.3. Identification of Main Scenarios for Representative Cases2.1.1.2.3.1. Full Power ConditionsFamily 1: SB(LOCA) and SGTR with partial and fast secondary cooldown (Table 7).[Ref]A Caillaux. EPR RF002. Severe Accident. 5.5.2 In-vessel analysis. Hydrogen SourceTerm. NFEPD DC 0059 Revision B. Framatome ANP. January 2004. (E)SGTR: core melt scenario[Ref]P Gandrille. EPR RF002. Severe Accident. In-vessel MAAP 4 study for containment bypassradiological releases. NFEPD DC 0053 Revision B. Framatome ANP.January 2004. (E)Family 2: LB(LOCA) and SB(LOCA) with partial secondary cooldown only (Section16.2.2.1 - Table 8[Ref]A Caillaux. EPR RF002. Severe Accident. 5.5.2 In-vessel analysis. Hydrogen SourceTerm. NFEPD DC 0059 Revision B. Framatome ANP. January 2004. (E)Family 3: Scenarios without RCS break and with SG dryout (Section 16.2.2.1 - Table 9)[Ref]P Gandrille. EPR RF002. Severe Accidents. Dedicated Reactor Coolant SystemDepressurisation. Functional requirements. NFEPD DC 0091 Revision C.Framatome ANP. August 2004. (E)2.1.2. Selection of Relevant Scenarios to Design Mitigation Features2.1.2.1. Prevention of High Pressure Core Melt Scenarios2.1.2.1.2. Reference Scenarios[Ref]P Gandrille. EPR RF002. Severe Accidents. Dedicated Reactor Coolant SystemDepressurisation. Functional requirements. NFEPD DC 0091 Revision C.Framatome ANP. August 2004. (E)
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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