An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance

Kelly, Dana; Jones, Kenneth R.; Dallman, R.J.; Wagner, Kenneth Charles

doi:10.2172/6675119

Cited by 1 publication

(16 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Nevertheless, consideration of the predictions afforded by these simple hand calculations is useful in providing a basis for understanding the specific code results that will be discussed in Chap. 19. There it will again be seen that although Ihe bottom head comprises two-thirds of the debris bed surface area (and is effectively cooled), less than two-thirds of the total heat transfer from the bed would follow this pathway.…”

Section: Physicalmentioning

confidence: 90%

“…Lower plenum debris bed and vessel wall response at time 300 min after scram for base case 19.4 Lower plenum debris bed and vessel wall response at time 360 min after scram for base case 135 19.5 Lower plenum debris bed and vessel wall response at time 420 min after scram for base case 19.6 Lower plenum debris bed and vessel wall response at time 480 min after scram for base case 19.7 Lower plenum debris bed and vessel wall response at time 540 min after scram for base case NVREG/CR-5869 x 19.8 Lower plenum debris bed and vessel wall response at time 600 min after scram for base case 19.9 Lower plenum debris bed and vessel wall response at time 660 min after scram for base case 19.10 Lower plenum debris bed and vessel wall response at time 711) min after scram for base case 19.11 Lower plenufA debris bed and vessel wall response at time 780 min after scram for base case 19.12 Lower plenum debris bed and vessel wall response at time 840 min after scram for base case 19. 13 Tables Table Page ES…”

Section: List Of Figuresmentioning

confidence: 99%

“…Considering the Peach Bouom plant configuration and assuming the use of Polybor® to take advantage of its greater solubility. 19.300 Ib (8,750 kg) would have to be added to the partially drained tank.…”

Section: Nureg/cr-5869 XXIVmentioning

confidence: 99%

“…These events have been considered in the calculations discussed in this report, and their effects will be described in detail in Chap. 19. The reduction of the total decay power with time is determined in accordance with the recommendations of Ostmeyer.…”

Section: Recirculation Pump Suction Nozzlementioning

confidence: 99%

“…The calculations are based upon the short-term station blackout accident sequence, which is described in Sect. 19 If a Peach Bottom unit were operating at 100% power when station blackout occurred and if both high-pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) were to fail upon demand, then the swollen reactor vessel water level would fall below the top of the core in -40 min. After the core is uncovered, events would progress rapidly because the decay heat level is relatively high for the short-term station blackout accident sequence.…”

Section: The Vesse) Drainmentioning

confidence: 99%

See 4 more Smart Citations

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

Hodge¹,

Kress²,

Cleveland³

et al. 1992

View full text Add to dashboard Cite

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.

show abstract

Section: Physicalmentioning

confidence: 90%

Section: List Of Figuresmentioning

confidence: 99%

Section: Nureg/cr-5869 XXIVmentioning

confidence: 99%

Section: Recirculation Pump Suction Nozzlementioning

confidence: 99%

Section: The Vesse) Drainmentioning

confidence: 99%

See 3 more Smart Citations