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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 : 293 / 295Document ID.No.UKEPR-0002-162 Issue 043.2.4. Iodine behaviour in the containment[Ref][Ref][Ref][Ref]Störfallberechnungsgrundlagen für die Leitlinien des BMI zur Berurteilung derAuslegung von Kernkraftwerken mit DWR gemäß §28 Abs. 3. StrlSchV,Veröffentlichung der Strahlenschutzkommision, Band 1, 1989.[Incident Calculation Bases for the Guidelines Issued by the Federal Minister of theInterior (BMI) for the assessment of the design of PWR Nuclear Power Plants pursuantto Sec. 28, para. (3) of the Radiological Protection Ordinance (StrlSchV)] 1989 (E)K H Neeb. The Radiochemistry of Nuclear Power Plants with Light Water Reactors.Walter de Gruyter, Berlin, New York. 1997. (E)Iodine Chemical forms in LWR <strong>Severe</strong> <strong>Accident</strong>s. NUREG/CR-5732. 1992. (E)L Soffer, et al. <strong>Accident</strong> Source Terms for Light-Water Nuclear Power Plants.NUREG-1645. 1992. (E)3.2.5. Activity release from the containment[Ref]C Cherbonnel. Hypothesis to be used for evaluating the radiological consequences ofdesign basis accident – <strong>Analysis</strong> of the ability of the different ventilation systems toreduce the fission products releases. ENFPIN/0100177 Revision A1. <strong>EDF</strong>.September 2009. (E)ENFPIN/0100177 Revision A1 is the English translation of ENFPIN/0100177 Revision A3.2.6. Release of Radioactive Substances to the Environment[Ref]D Chanin, M L Young. Code Manual for MACCS2: Volume 1, User’s Guide.NUREG/CR-6613. SAND97-0594, Volume. 1, Sandia National Laboratories,Albuquerque, NM, USA. 1998. (E)3.3. CALCULATION OF RADIOLOGICAL CONSEQUENCES[Ref]Störfallberechnungsgrundlagen für die Leitlinien des BMI zur Berurteilung derAuslegung von Kernkraftwerken mit DWR gemäß §28 Abs. 3. StrlSchV,Veröffentlichung der Strahlenschutzkommision, Band 1, 1989.[Incident Calculation Bases for the Guidelines Issued by the Federal Minister of theInterior (BMI) for the assessment of the design of PWR Nuclear Power Plants pursuantto Sec. 28, para. (3) of the Radiological Protection Ordinance (StrlSchV)]. 1989. (E)[Ref] International Commission on Radiological Protection: ICRP Publication 56.Age-Dependent Doses to the Public from Intake of Radionuclides; Part 1; 1990. (E)1990 Recommendations of the International Commission on Radiological Protection.ICRP Publication 60. Ann. ICRP 21 (1-3). 1991. (E)ICRP Publication 67. Age-Dependent Doses to Members of the Public from Intake ofRadionuclides; Part 2; Ingestion Dose Coefficients 1990. 1994. (E)ICRP Publication 69. Age-Dependent Doses to Members of the Public from Intake ofRadionuclides; Part 3; Ingestion Dose Coefficients.1995. (E)

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