Predication of the SMR Critical Core Performance Under Zero Power

Magy Kandil Salwa Helmy Ahmed Refaey
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Abstract

In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.
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零功率下SMR临界堆芯性能预测
在核电站中,反应性诱发事故可能导致严重的事故。抽油杆弹射事故是反应性诱发事故的一部分,是由于许多故障由反应性插入驱动引起的。因此,对核电厂许多外棒反应下堆芯行为的安全分析是监管机构或安全当局的强制性要求。在本研究中,提出了一种新的抽杆事故下堆芯安全分析的动态模型。对于任何反应堆运行政策来说,在所有时期,特别是在零功率状态下,热功率和其他堆芯参数的预测都是最重要的目标,以避免发生严重事故。该模型涉及中子点动力学解释,结合堆芯内的热工水力动力学,在MATLAB环境下预测堆芯瞬态参数的变化。通过与NuScale小型模块化反应堆设计方案的瞬态动态响应对比,验证了所提模型的有效性。此外,通过对热零功率下不同控制棒弹射的多摄动情况下的反应堆动态响应进行了验证。已执行的安全性分析验证和验证结果表明,所提出的模型能较好地预测堆芯抛射瞬态时的堆芯行为,并能较好地预测堆芯峰值的热功率。此外,它还允许对堆芯安全参数进行大量探索,并在临界热零功率下预测其矢量堆芯在棒弹射事故中的性能。
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