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 : 275 / 295Document ID.No.UKEPR-0002-162 Issue 04SUB-CHAPTER 16.2 – REFERENCESExternal references are identified within this sub-chapter by the text [Ref] at the appropriatepoint within the sub-chapter. These references are listed here under the heading of the sectionor sub-section in which they are quoted.0. SAFETY OBJECTIVES0.1. GENERAL[Ref][Ref]Technical Guidelines for the design and construction of the next generation of nuclearpower plants with pressurized water reactors. Adopted during the GPR/German expertsplenary meetings. October 19th and 26th 2000. (E)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 inNovember 1992, Oxford, New York, Seoul, Tokyo. ICRP Publication 63. ICRP. 1993. (E)1. APPROACH TO SEVERE ACCIDENT CONTROL1.1. BASIC STRATEGY[Ref]D Struwe et al. Consequence evaluation of In-vessel Fuel Coolant Interaction in theEuropean Pressurized Water Reactor. FZK Final Report No. 6316. 1999. (E)1.3. SPECIAL ISSUES1.3.1. Steam explosion1.3.1.1. In-vessel steam explosion[Ref]B De Boeck. Introduction to Severe Accidents. O/Ref. 97-2589.DOC, Class. XP.00.NSAVN-97/013. 1997.1.3.1.1.1. Involved Physical Phenomena[Ref] Technical Opinion Paper on Fuel-Coolant Interaction. NEA/CSNI/R(99)24. OECD. 1999.(E)
SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 276 / 295Document ID.No.UKEPR-0002-162 Issue 041.3.1.1.1.4. Expansion Phase[Ref]Leon Cizelj et al. Vulnerability of partially flooded PWR reactor cavity to a steamexplosion. Nuclear Engineering and Design, Volume 236 (August 2006), pp. 1617-1627.“Jozef Stefan” Institute. 2005. (E)1.3.1.1.2. Insights from Previous Studies[Ref]N Rasmussen. Reactor Safety Study. WASH-1400 (NRC). 1975. (E)1.3.1.1.2.1. Pressure Influence[Ref]R E Henry. Overview: Uncertainties Remaining in Severe Accident Phenomenology.MSC\N19. Fauske & Associates Inc. 1995. (E)1.3.1.1.2.2. Mixing Behaviour[Ref]R E Henry and H K Fauske. A different approach to Fragmentation in Steam Explosions.Fauske & Associates Inc. MSC\N14. 1996. (E)1.3.1.1.2.3. Influence of Particulate Debris and Steam Generation[Ref][Ref]T Morii et al. Benchmark Analysis of Premixing Phase of FCI Experiment by theVESUVIUS Code. The 10 th International Topical Meeting on Nuclear Reactor ThermalHydraulics. NURETH-10. 2003. (E)US-NRC. TMI-2 Vessel Investigation Project. SECY-93-119. 1993. (E)1.3.1.1.3. US-NRC Studies[Ref]R E Henry. Overview: Uncertainties Remaining in Severe Accident Phenomenology.Fauske & Associates Inc. MSC\N19. 1995. (E)[Ref] B R Sehgal et al. Pre-Project on Development and Validation of Melt Behaviour inSevere Accidents. NKS-99. ISBN 87-7893-158-4. 2004. (E)[Ref][Ref]T G Theofanous, W W Yuen and S Angilini. The verification basis of the PM-ALPHAcode. Nuclear Engineering and Design Volume 189, 59-102. 1999. (E)N Rasmussen. Reactor Safety Study. WASH-1400 (NRC). 1975. (E)1.3.1.1.4. Recent European Studies[Ref][Ref][Ref]B R Sehgal et al. Pre-Project on Development and Validation of Melt Behaviour inSevere Accidents. NKS-99. ISBN 87-7893-158-4. 2004. (E)B R Sehgal. Accomplishments and challenges of the severe accident research. NuclearEngineering and Design, Volume 210, 79-94. Elsevier. 2001. (E)A simplified approach to estimating reference source terms for LWR designs.TECDOC-1127. IAEA. 1999. (E)
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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