Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR

Taisei Matsumoto, A. Yamaji, D. Fujiwara
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Abstract

According to accident of a Boiling Water Reactor (BWR), the operators generally do not depressurize the Reactor Pressure Vessel (RPV) until low-pressure core injection systems are recovered. However, when the core water level decreases below a certain limit, the RPV is depressurized to prevent the RPV failure at high pressure, which may lead to failure of the Primary Containment Vessel (PCV) by direct heating of the ejected melt. In such a case, if recovery of the core cooling cannot be expected, earlier depressurization may be preferable from the viewpoint of reducing thermal load on PCV, because it may effectively reduce the amount of fission product (FP) aerosol deposition on the RPV dome and reduce the risk of PCV top head heating via convective and radiative heat transfers from the RPV dome. However, significance of such risk is not evident as the steam dryer and separator may hinder direct aerosol deposition on the RPV dome and the RPV dome is thermally insulated. Moreover, the narrow space between the RPV dome and the PCV top head may hinder convective heat transfer. In this study, sensitivity analyses have been carried out using MELCOR-2.2 to support such understanding.
沸水堆重大事故降压时机对主安全壳热负荷影响的评价
根据沸水反应堆(BWR)事故的经验,在低压堆芯注入系统恢复之前,操作人员通常不会给反应堆压力容器(RPV)减压。然而,当堆芯水位下降到一定限度以下时,对反应堆进行减压,以防止反应堆在高压下失效,从而通过直接加热喷出的熔体可能导致主安全壳(PCV)失效。在这种情况下,如果不能预期堆芯冷却的恢复,从减少堆载堆热负荷的角度来看,更早的降压可能是可取的,因为它可以有效地减少堆载堆圆顶上裂变产物(FP)气溶胶沉积的数量,并减少堆载堆顶部通过对流和辐射传热加热的风险。然而,这种风险的重要性并不明显,因为蒸汽干燥器和分离器可能会阻碍气溶胶直接沉积在RPV圆顶上,而RPV圆顶是隔热的。此外,RPV顶盖与PCV顶盖之间的狭窄空间可能会阻碍对流换热。在本研究中,使用MELCOR-2.2进行敏感性分析来支持这种理解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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