RAMONA-3B calculations for Browns Ferry ATWS (Anticipated Transient Without Scram) study

Saha, Pankaj; Slovik, G.C.; Neymotin, L.

doi:10.2172/6614081

Cited by 1 publication

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“…The general results and recommendations of the three main divisions of the report are summarized in Chap. 22.…”

Section: Nureg/cr-5869mentioning

confidence: 99%

“…8 This candidate strategy has been selected for detailed assessment, the results of which are provided in Chaps. 14 through 22. From the standpoint of providing the necessary volume of water, implementation would require the avail-Candidate ability of an independent drywell flooding system of sufficient capacity to deliver the required amount of water before reactor vessel lower plenum dryout and bottom head penetration failure.…”

Section: Wetwell Trapped Airspacementioning

confidence: 99%

“…20.2). 22. Drywell flooding with complete venting of the reactor vessel support skirt would serve to maintain the core and structural debris within the vessel.…”

Section: Water Surrounding the Reactor Vessel Bottom Headmentioning

confidence: 99%

“…7.1). 22. The availability of information concerning plant status is much greater for accident sequences such as shortterm station blackout [with mechanical failure of highpressure coolant injection (HPCI) and reactor core isolation cooling (RCIC)], ATWS, loss-of-coolant accident (LOCA), or loss of decay heat removal for which electrical power is maintained after loss of reactor vessel injection capability (Sect.…”

mentioning

confidence: 99%

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Identification and assessment of BWR in-vessel severe accident mitigation strategies

Hodge¹,

Kress²,

Cleveland³

et al. 1992

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This report provides the results of work carried out in support of the U.S. Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident managemenl First. the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners' Group Emergency Procedure Guidelines (EPGs) to detennine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for 111 recommendations for enhancement of accident management procedures. Second. where considered necessary. new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally. recommendations are made for consideration of additional strategies where warranted. and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored.

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“…The general results and recommendations of the three main divisions of the report are summarized in Chap. 22.…”

Section: Nureg/cr-5869mentioning

confidence: 99%

Section: Wetwell Trapped Airspacementioning

confidence: 99%

“…20.2). 22. Drywell flooding with complete venting of the reactor vessel support skirt would serve to maintain the core and structural debris within the vessel.…”

Section: Water Surrounding the Reactor Vessel Bottom Headmentioning

confidence: 99%

mentioning

confidence: 99%

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