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Analysis of unprotected loss of heat sink accident in compact high temperature reactor cooled under natural circulation of LBE coolant

机译:小型高温反应器中的散热器事故未受保护损失的分析,冷却液体冷却液冷却

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India is developing 100kW(th) Compact High Temperature Reactor (CHTR) to demonstrate the technology enabling high-temperature process heat applications such as hydrogen production. The reactor core is envisaged with 233U-Th based TRISO coated fuel particles and beryllium oxide moderator in prismatic fuel assemblies for high-temperature operation. The core heat is designed to be removed by lead-bismuth eutectic (LBE) coolant under natural circulation in vertical channels of CHTR at nominal power. The heat generated in the primary circuit is to be transferred to the secondary side using high-temperature sodium heat pipes. The design and safety of the prototype core necessitate comprehensive, integrated neutronics-thermal hydraulics analyses of anticipated transients. In this context, the Unprotected Loss of Heat Sink Accident (ULOHSA) at full power during the beginning of the core life cycle is investigated with indigenous 3D multi-physics code ARCH-TH. The key parameters defining neutronics and thermal-hydraulics of the core have been assessed in the steady-state as well as during the transient. The findings, along with the model of the simulation and the code validation are discussed in this paper. The analyses indicate that the core is being shut down passively due to reactivity feedbacks and the loss of heat sink leads to reverse flow of the coolant in the low powered channels during the transient. However, the coolant and fuel peak temperatures are observed to stay well below the leak-tightness limit of TRISO particles and boiling point of LBE, even considering the failure of shutdown systems. The modifications in the design of CHTR are also investigated to pacify the condition of flow reversal during such transients.
机译:印度正在开发100kW(TH)紧凑的高温反应器(CHTR),以证明技术实现高温工艺热应用,如氢气生产。在棱镜燃料组件中,用233U-T基三涂层的燃料颗粒和铍氧化物调节器设想反应器核心,用于高温操作。芯热设计用于在标称动力下在CHTR的垂直通道下的自然循环下通过引导铋共晶(LBE)冷却剂除去。初级回路中产生的热量将使用高温钠热管转移到次级侧。原型核心的设计和安全性需要综合,集成的中型 - 热液压分析预期瞬态。在这种情况下,利用土着3D多物理代码拱门研究了在核心生命周期开始时全功率的无保护丢失损失(ULOHSA)。在稳态和瞬态期间,已经评估了定义中型和热液压的关键参数和核心的热液压。在本文中讨论了该研究结果以及模拟和代码验证的模型。分析表明,由于反应性反馈,核心被动地被动地关闭,并且在瞬态期间,散热器的丢失导致冷却剂的逆转。然而,观察到冷却剂和燃料峰值温度以远低于Triso颗粒和LBE的沸点的泄漏密封极限,甚至考虑关闭系统的故障。还研究了CHTR设计中的修改,以在这种瞬变期间安抚流动逆转的条件。

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