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首页> 外文期刊>Annals of nuclear energy >Feasibility analysis of aggressive cooldown in OPR-1000 nuclear power plants
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Feasibility analysis of aggressive cooldown in OPR-1000 nuclear power plants

机译:OPR-1000核电厂进行主动冷却的可行性分析

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Aggressive cooldown is the action taken by main control room (MCR) operators to rapidly cool down and depressurize the reactor coolant system at the maximum allowed cooldown rate during a small break loss of coolant accident (SBLOCA) or a steam generator tube rupture accident with failure of high-pressure safety injection (HPSI) in a pressurized water reactor. We examined the feasibility of aggressive cooldown in OPR-1000 nuclear power plants by establishing success criteria based on experimental results and thermal-hydraulic code simulations, reviewing emergency operating procedures, and estimating the necessary time for MCR operators to initiate aggressive cooldown based on experimental results with licensed nuclear power plant operators. For an SBLOCA with a break size of 0.02 ft~2 combined with total failure of HPSI, we found that aggressive cooldown can generally be performed successfully, but there is potential for failure to initiate aggressive cooldown in a timely manner. We discuss the potential effects of introducing the Ultimate Procedure on reducing the core damage potential. Detailed analysis and further discussion are necessary to reduce uncertainties associated with aggressive cooldown and its positive effect on the safety of nuclear power plants.
机译:激进的冷却是主控制室(MCR)操作员采取的措施,以在冷却剂发生小断裂损失事故(SBLOCA)或蒸汽发生管破裂故障并发生故障时,以最大允许的冷却速率对反应堆冷却剂系统进行快速冷却和减压压水反应堆中高压安全注入(HPSI)的分析。我们通过基于实验结果和热工液压代码模拟建立成功标准,审查应急运行程序并根据实验结果估算MCR运营商启动主动冷却的必要时间,研究了OPR-1000核电厂主动冷却的可行性与有执照的核电厂运营商合作。对于断裂尺寸为0.02 ft〜2且HPSI完全失效的SBLOCA,我们发现主动冷却通常可以成功进行,但可能无法及时启动主动冷却。我们讨论了引入“终极程序”对减少核心损害可能性的潜在影响。为了减少与激进冷却有关的不确定性及其对核电厂安全的积极影响,有必要进行详细分析和进一步讨论。

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