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安全壳内MSLB事故下的质能释放与安全壳行为分析 总被引:2,自引:0,他引:2
基于18个月换料的堆芯设计,利用THEMIS程序计算了大亚湾核电站1、2号机组在安全壳内发生主蒸汽管道断裂事故(MSLB)下的质能释放(MEB)量。以此为边界条件,利用PAREO9程序对安全壳的响应做了分析。分析认为,在假想的MSLB事故下,安全壳的完整性有保障。 相似文献
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针对ACP600取消高压安注系统和浓硼箱、使用一体化钆为可燃毒物、采用Mode-C运行与控制模式等设计改进导致主蒸汽管道破裂(MSLB)事故安全裕量降低的不利情况,对先进三代核电厂ACP600的MSLB事故进行分析研究。为避免MSLB事故下反应堆重返临界后堆芯功率峰值过高导致偏离泡核沸腾比(DNBR)低于限制值,分别从快速注入硼溶液和减缓堆芯冷却率的角度,评价不同的安注系统配置以及停运故障环路主泵对于缓解MSLB事故的作用。研究最佳的缓解方案,并提出增设“蒸汽管线压力低-3”信号停运故障环路主泵的设计优化建议。 相似文献
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针对更为精细和准确的堆芯建模与热工水力分析需求,基于自主研发的Non LOCA热工水力分析程序GINKGO和三维物理程序COCO,采用动态链接库(DLL)技术开发了GINKGO/COCO耦合程序;介绍了耦合程序的开发原理和实现方式,并采用经济合作与发展组织(OECD)主蒸汽管道破裂事故(MSLB)国际基准题对其进行了验证。结果表明,GINKGO/COCO耦合程序的计算结果与OECD MSLB国际基准题的结果较为吻合。因此,GINKGO/COCO耦合程序具有良好的计算能力和可靠性。 相似文献
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主蒸汽管道断裂(MSLB)事故威胁核电厂安全运行。本文基于时序深度学习模型预测核电厂非能动安全壳冷却系统(PCCS)在MSLB事故下关键安全参数随时间变化的瞬态响应。以瞬态安全参数为研究对象,数据通过线性归一化、特征标签分割预处理,使用短期数据集训练,采用长短时记忆网络(LSTM)和循环神经网络(RNN)建立单参量与多参量协同的时序深度学习模型;由多参量协同模型预测未经训练的长期数据集。研究表明:在同类事故、不同工况下,基于时序深度学习模型的预测具有适用性;基于训练短期数据来预测长期数据方法可行;使用LSTM的单参量模型或多参量协同模型的预测精度比RNN更高,基于LSTM深度学习模型能够有效、高精度快速预测MSLB事故下PCCS瞬态安全参数响应特性, 可为事故安全分析提供快速预测分析。 相似文献
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本文对拟建于严寒地带的红沿河核电厂CPR1000机组中主蒸汽管道和主给水管道(VVP/ARE)隔室与外界环境之间的封堵进行了设计改造,并对改造后方案的隔室墙体重新进行由隔室内管道破裂引起的超压风险分析论证。采用隔室热工响应分析程序对不同封堵方案进行计算分析,对比分析了不同封堵方案下不同隔室发生主蒸汽管道双端剪切断裂(MSLB)事故后的超压后果,论证了封堵方案的可行性。文中还针对封堵方案进行了敏感性研究,并给出了最佳封堵方案。该封堵方案已在红沿河核电厂实施。 相似文献
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对大破口失水事故(LOCA)下的质能释放计算程序MEDUSE、PERSEE、REFLET,以及主蒸汽管道断裂事故(MSLB)下的质能释放计算程序THEMIS作了介绍,并对程序模型进行简要说明.对秦山核电二期工程的大破口失水事故和主蒸汽管道断裂事故工况下的质能释放进行计算分析.计算结果表明对质能释放而言,主蒸汽管道断裂事故工况最恶劣. 相似文献
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Because of the strong asymmetric overcooling effects occurring during a PWR main steam line break (MSLB) event, an accurate analysis of this transient requires the use of 3-D kinetics methods. An assessment has been made of the relative performance of the two kinetics solvers currently employed at PSI for such analyses, viz. CORETRAN and SIMULATE-3 K. For the purpose, the simulation of a hypothetical MSLB in a real operated PWR MOX cycle has been considered, employing consistent 3-D core models with specified thermal-hydraulic boundary conditions at the lower and upper plenums. Although the employed cross-section library is in both codes based on the same set of homogenised 2-group cross-sections prepared with CASMO-4, significant differences are shown to occur due to the smaller moderator reactivity coefficient calculated in CORETRAN. It is found that this stems largely from differences in the cross-section formalism, i.e. the manner in which feedback dependencies are modelled and interpolated for the cross-section sets.In particular, the CORETRAN cross-section formalism induces an inadequate treatment of coupled feedback effects, principally between boron density and moderator temperature, which renders the MSLB dynamics predictions quite sensitive to the methodology employed during the cross-section preparation. As such, transient-specific cross-section libraries need to be produced for reliable MSLB analysis in this case. The cross-section model for SIMULATE-3 K, on the other hand, is shown to be adequate for accurately capturing the coupled reactivity effects occurring during an MSLB. In this case, the sensitivity of the results to other sources of uncertainties becomes more apparent, e.g. to those related to the neutron data and/or the thermal-hydraulic boundary conditions. Considering that many other state-of-the-art advanced kinetics solvers have cross-section formalisms similar to that of CORETRAN, effects of the type currently investigated need to be taken into account while developing methodologies for assessing neutronics-related uncertainties in best-estimate transient analysis. 相似文献
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In boiling water reactor (BWR) design, significant acoustic pressure loads impact the steam dryer hood as a result of the main steam line break outside containment (MSLB) event. When a main steam line breaks, it is assumed that the pipe instantaneously breaks completely open to the ambient environment (double-ended guillotine break). Due to the huge pressure difference between the inside of the reactor pressure vessel (RPV) and surrounding ambient environment, a shock wave will form at the break point and burst into the surrounding environment. At the same time, an expansion wave will travel upstream through the main steam line to the RPV, which results in a pressure reduction on the outside of the steam dryer hood. This expansion wave will create a substantial pressure difference between the two sides of the steam dryer hood with a resultant high stress on the hood. This differential pressure load is the acoustic load used in the structure design evaluations for this event. A key design basis requirement for the steam dryer is to maintain structural integrity during transient, and accident conditions. Demonstration that the steam dryers meet this design basis requires a calculation of the magnitude of the acoustic load on the steam dryer during a MSLB. In this study, computational fluid dynamics (CFD) is used as an alternate calculation method to investigate the phenomenon of MSLB. Transient simulations with fine time steps were carried out. The results show that CFD is a useful tool to provide additional information on the acoustic load as compared to the traditional methods. From the CFD results, the minimum pressure value and its distribution area at different flow times was identified. Through the modeling, an understanding of the detailed transient flow field, particularly the acoustic pressure field near the dryer hood during the MSLB was achieved. 相似文献
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基于经典的“两步法”压水堆计算流程,采用目前最先进的核反应堆物理计算方法,研发了先进的压水堆燃料管理软件Bamboo-C。Bamboo-C软件主要由3个功能程序(LOCUST、SPARK、LtoS)组成,LOCUST为二维组件非均匀及等效均匀化计算程序,SPARK为三维堆芯稳态/瞬态分析程序,LOCUST和SPARK程序之间通过组件均匀化参数函数化程序LtoS链接。Bamboo-C软件具备完善的压水堆燃料管理与核设计必备的分析功能,主要包括:启动物理试验、动力学参数计算、控制棒微积分价值、功率运行跟踪等。最后,基于我国自主研发的CNP300、CNP650和CNP1000堆型的运行数据,完成了Bamboo-C软件的工业确认工作。结果表明,采用Bamboo-C软件获得的临界硼浓度、温度系数、控制棒价值以及功率分布等堆芯关键参数的计算值与实测值之间的误差均满足工业限值的要求。 相似文献
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通过使用RELAP5/MOD2程序对秦山核电厂主蒸汽管道破裂事故的计算,对该程序的临界流模型和传热模型进行分析,并与其它大型热工水力分析程序的计算结果及实验结果进行比较。在计算过程中,对RELAP5/MOD2程序汽水分离器模型的使用进行修正,使之符合核电厂安全评审计算的要求。 相似文献