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Modeling and Simulation for Coolant Activity and Dose Rate Estimation in a Pool-Type Nuclear Research Reactor

机译:池型核研究堆中冷却剂活度和剂量率估算的建模与仿真

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Coolant activity in the primary coolant system and reactor pool in an open pool-type research reactor is very important in view of operational and radiological safety considerations. As pool water acts as the shielding medium to minimize the radiation dose at the top of the reactor pool, an estimation of the activities of radionuclides in pool water is essential to establish the safety of the operating personnel and researchers working at the reactor pool top. A system is provided to create a hot water layer (HWL) at the top of the pool by supplying water at a temperature more than that of the pool water so that the dose rate at the reactor pool top can be minimized. This HWL system helps in breaking the natural convection current of reactor pool water by maintaining a higher temperature at this layer so that high-density pool water below this layer cannot replace this low-density HWL. Therefore, pool water that is comparatively more radioactive will not be able to cross this HWL by convection. Hence, diffusion will be the only mechanism by which radioactivity can reach the pool top. So eliminating the convection current keeps the activity at this topmost layer of the pool at a minimum value. The estimation of the activity of the radioactive nuclides is required to assess the radiation field at different locations in the primary coolant loop for designing proper shielding requirements of the system. The radionuclides of interest are the activation products of aluminum (Na-24, Mg-27, Al-28) and Ar-41. In this technical note, a transient code is presented for estimating the activity of radioactive nuclides in the coolant loop and reactor pool of a nuclear research reactor. The reduced activity level at the pool top is estimated considering the presence of the HWL at the top of the pool. It is observed that purification flow plays a major role on the activity level of radioactive nuclides in reactor pool water. The variation of the activity dose rate at the reactor pool top with purification flow is also discussed.
机译:考虑到操作和放射安全考虑,开放式池型研究堆中主冷却剂系统和反应堆池中的冷却剂活性非常重要。由于池水充当了屏蔽介质,可最大程度地减少反应堆池顶部的辐射剂量,因此估算池水中放射性核素的活性对于建立在反应堆池顶部工作的操作人员和研究人员的安全至关重要。提供了一种系统,该系统通过供应温度高于池水温度的水在池顶部创建热水层(HWL),从而可以使反应器池顶部的剂量率最小化。该HWL系统通过在该层保持较高的温度来帮助打破反应堆池水的自然对流,从而使该层以下的高密度池水无法替代该低密度HWL。因此,放射性较高的池水将无法通过对流穿过该HWL。因此,扩散将是放射性到达池顶的唯一机制。因此,消除对流电流可使池的最顶层的活动保持在最小值。为了设计系统的适当屏蔽要求,需要估算放射性核素的活性以评估一次冷却剂回路中不同位置的辐射场。感兴趣的放射性核素是铝(Na-24,Mg-27,Al-28)和Ar-41的活化产物。在此技术说明中,提供了一个瞬态代码,用于估算核研究反应堆冷却剂环路和反应堆池中放射性核素的活动。考虑到池顶HWL的存在,可以估计池顶活动水平的降低。观察到净化流对反应堆池水中放射性核素的活性水平起主要作用。还讨论了反应器池顶部活性剂量率随纯化流量的变化。

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