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首页> 外文期刊>Annals of nuclear energy >Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels
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Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels

机译：用低浓铀和高浓铀分散燃料为燃料的材料试验研究堆的流动瞬态失控损失模拟

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The effects of using low and high enrichment uranium fuel on the uncontrolled loss of flow transients in a material test research reactor were studied. For this purpose, simulations were carried out of an MTR fuelled separately with LEU and HEU fuel, to determine the reactor performance under loss of flow transients with totally failed external control systems. The coolant pump was assumed to loose its performance and the coolant flow rate reduced according to the relation m(t)/m_0 = exp(-t/25) to a new stable level. The new reduced flows m/m_0 = 0.2, 0.4, 0.6 and 0.8 were modeled. The nuclear reactor analysis code PARET was employed to carry out these calculations. It was observed that the reactors stabilized at new power levels which were lower than the original power level, with the power of HEU fuelled reactor slightly lesser than that of the LEU fuelled reactor. However, at the start of transient, the LEU fuelled reactor had a lower power level resulting in lower fuel, clad and coolant temperatures than the HEU fuelled reactor.
机译：研究了在材料试验研究堆中使用低浓铀燃料和高浓铀燃料对流动瞬态失控损失的影响。为此，对分别用低浓铀和高浓铀燃料供油的MTR进行了模拟，以确定在外部控制系统完全失效的情况下，在瞬变损失的情况下反应堆的性能。假定冷却剂泵性能下降，并且冷却剂流量根据关系m（t）/ m_0 = exp（-t / 25）降低到新的稳定水平。对新的减少流量m / m_0 = 0.2、0.4、0.6和0.8进行了建模。使用核反应堆分析代码PARET进行这些计算。观察到，反应堆稳定在新的功率水平，该水平低于原始功率水平，高浓铀燃料反应堆的功率略低于低浓铀燃料反应堆的功率。但是，在过渡开始时，与HEU燃料反应堆相比，LEU燃料反应堆的功率水平较低，导致燃料，包层和冷却液温度更低。

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