Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

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Extra info for Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

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Oct. 1993). Light Water Reactor Lower Head Failure Analysis, NUREG/CR-5642, EGG-26 18. L. L. Humphries (1994). Lute Phase Melt ProgressionScoping and SensitivityStudies, Draft, SAMD82-2831. W. et id. 1994). Fragmentation and Quench Behavior of Corium Melt Streams in Water, NUREGKR-6133, ANL-93/32. Sticklzr, L A . et al. (Oct. 1993). calculations to Estime the Margin to Failure in the IUI-2 Vessel, TMI V(93)EGUl. (1988). "Some Considerations of Severe Accidents at Loviisa," Report Prepared for Imatro~Voima 04,Helsinki, Finland.

With this traditional understanding, containment- threatening loads from DCH can only be precluded if the RCS is almost fully depressurized. However, based on the understanding developed in NUREG/CR4075 (Pilch et al. 1994a), a substantial reduction of DCH is achieved without having to invoke nearly complete depressurization of the RCS. Quantification of melt release conditions was developed by attempting to envelope the physically possible behavior in a comprehensiveand systematic manner. This means that we needed to examine all reasonably conceivable severe accident scenarios, identify key aspects of their phenomenology and respective ranges of behavior, i-kd establish the few scenarios that envelope the DCH challenge to the containment.

Consequently, the initial steam concentration is -48 percent. , fan coolers or sprays) are not operational. 079. Thus, there - - - was little steam in the containment. This situation will also be analyzed in Section 6. The core-wide oxidation of Zr also controls the amount of preexisting hydrogen that can exist in the containment building at the time of vessel breach. The RCS retains very little of this hydrogen because it is produced early in the accident and most is vented to the containment.

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