SBLOCA outside containment at Browns Ferry Unit One: accident sequence analysis. [Small break]

Technical Report · Mon Nov 01 00:00:00 EST 1982

OSTI ID:6669291

Condon, W A; Harrington, R M; Greene, S R; Hodge, S A

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.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6669291
• Report Number(s): NUREG/CR-2672-Vol.1; ORNL/TM-8119/Vol.1; ON: DE83003191
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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HYDRAULICS
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NONMETALS
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