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Large Break Loss of Coolant Accident Analysis of VVER-1000 reactor using CATHARE Code

机译:使用Cathare Code的Vver-1000反应器的冷却液事故分析的大休损失

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In the safety analysis of the nuclear power plants Large Break Loss of Coolant Accident continue to be one of the major issues. In this study the last version of the French best estimate computer code CATHARE2 V2.5_1 Mod 6.1 was used in order to predict the thermal-hydraulic phenomena in the VVER-1000 reactor during LB LOCA. This type of reactors are in operation and construction in several countries like Russia, Ukraine, Bulgaria, Czech Republic, China, India. The paper first presents the CATHARE modeling of VVER-1000 reactor, including the core, the vessel, the primary and secondary circuits with the pressurizer, main circulation pumps, horizontal steam generators and steam lines. The ECCS is presented also with hydroaccumulators, high pressure and low-pressure safety injection pumps. The break, located in the cold leg, close to the reactor, is represented by the RUPTURE module of CATHARE, which modelizes a double ended guillotine type of break. In the current calculations the Bottom-up and Top-down reflooding play a very important role, compared to some western PWR, because of the ECCS injection into the downcomer and upper plenum of the VVER-1000. That is why special attention is paid to the validation of the CATHARE reflooding model, based on REWET-II experiment, devoted to VVER. In CATHARE a special 2D reflooding module has been developed, which takes into account the radial and axial conduction in the vicinity of the quench front. Then, the paper presents the results of the LB LOCA analysis for VVER-1000 (reference case and sensitivity study), describing the blowdown, refill and reflood phase of the accident. Problems, related to the counter current flow limitation (CCFL) phenomena at the core outlet are considered also. Basic parameters, important to the safety of the plant, are illustrated: break flows, pressures, temperatures, void fractions and especially quench front propagation and maximal fuel cladding temperatures.
机译:在核电站的安全分析中,核发生物的大休损失事故丧失仍然是主要问题之一。在这项研究中,使用了法国最佳估计计算机代码Cathare2 V2.5_1 Mod 6.1的最后一个版本,以便在LB LOCA期间预测Vver-1000反应器中的热液压现象。这种类型的反应堆在俄罗斯,乌克兰,保加利亚,捷克共和国,中国,印度等几个国家进行了运行和建设。本文首先介绍了VVER-1000反应器的阴部建模,包括芯,船舶,初级和次电路,具有加压器,主循环泵,水平蒸汽发生器和蒸汽管线。 ECC也呈现出氢联器,高压和低压安全喷射泵。位于靠近反应器的冷腿中的断裂由阴部的破裂模块表示,其建造了双重结束的断头台类型的断裂。在目前的计算中,自下而上和自上而下的反射起着非常重要的作用,与一些西方PWR相比,因为ECCS注入VVER-1000的脱绒机和上层增压室。这就是为什么基于Rewet-II实验的基于Rewet-II实验,特别注意验证守护者的验证为什么,致力于Vver。在Cathare A中,已经开发了特殊的2D reshood模块,这考虑了淬火前方附近的径向和轴向传导。然后,本文介绍了VVER-1000(参考案例和敏感性研究)的LB LOCA分析的结果,描述了事故的排污,再填充和反射阶段。还考虑了与核心出口处的计数器电流流动限制(CCFL)现象有关的问题。阐述了植物安全性的基本参数:断裂流动,压力,温度,空隙级分,特别是淬火前传播和最大燃料包层温度。

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