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

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 : 22 / 295Document ID.No.UKEPR-0002-0162 Issue 04SUB-SECTION <strong>16.2</strong>.1.3.2.1 - TABLE 1In-Vessel Recriticality Configurations and ResultsStart of core degradationPhase 1Safety injection with IRWST boron concentrationpresents no recriticality risk, when fuel geometry isquite intact.Formation of a molten pool in the corePhase 2There are uncertainties regarding the effective coolablemass in low pressure degraded scenarios. Expectedcoolable mass like that at TMI-2, uniformly fragmentedat optimal porosity, presents no recriticality risk.In addition a higher amount of corium (although unlikelyto be coolable) may present no recriticality risk sinceoptimal and uniform porosity is not assured for largemasses.Relocation of the corium into the vessel lower headPhase 3In this configuration vessel failure cannot be prevented,but reflooding may fragment corium in the upper part.The expected coolable thickness presents norecriticality risk, because water penetration in thedebris bed is limited by steam production.

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