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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 : 16 / 295Document ID.No.UKEPR-0002-162 Issue 041.3.1.1.5. Resolution StatusThe conclusion from the NRC studies by SERG1 and SERG2 is that the α-mode failure dueto explosive corium-water interactions is not sufficient to rupture the primary system or thecontainment vessel and therefore this failure mode is very unlikely. This conclusion isconsistent with the results from several experimental studies performed in Europe andJapan.Therefore, this issue of in-vessel steam explosion is considered as definitely resolved,especially in new reactor designs such as the EPR, and hence additional measures withrespect to <strong>Accident</strong> Management Evaluations are not justified.

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