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- W98780879 abstract "This study describes the predicted response of Unit 1 at the Browns Ferry Nuclear Plant to a postulated small-break loss-of-coolant accident outside of the primary containment. The break has been assumed to occur in the scram discharge volume piping immediately following a reactor scram that cannot be reset. The events before core uncovering are discussed for both the worst-case accident sequence without operator action and for the more likely sequences with operator action. Without operator action, the events after core uncovering would include core meltdown and subsequent containment failure, and this event sequence has been determined through use of the MARCH code. An estimate of the magnitude and timing of the concomitant release of the noble gas, cesium, and iodine-based fission products to the environment is provided in Volume 2 of this report." @default.
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- W98780879 date "1982-11-01" @default.
- W98780879 modified "2023-10-03" @default.
- W98780879 title "SBLOCA outside containment at Browns Ferry Unit One: accident sequence analysis. [Small break]" @default.
- W98780879 hasPublicationYear "1982" @default.
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