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首页> 外文期刊>Nuclear engineering and technology >Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and long-term natural convection mode using the RELAP5/3.2 code
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Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and long-term natural convection mode using the RELAP5/3.2 code

机译：使用RELAP5 / 3.2代码在向下冷却池式材料测试反应器中针对完整站停电和长期自然对流模式对完整的被动排热系统进行仿真和瞬态分析

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In this paper, a complete station blackout (SBO) or complete loss of electrical power supplies is simulated and analyzed in a downward cooling 5-MW pool-type Material Testing Reactor (MTR). The scenario is traced in the absence of active cooling systems and operators. The code nodalization is successfully benchmarked against experimental data of the reactor's operating parameters. The passive heat removal system includes downward water cooling after pump breakdown by the force of gravity (where the coolant streams down to the unfilled portion of the holdup tank), safety flapper opening, flow reversal from a downward to an upward cooling direction, and then the upward free convection heat removal throughout the flapper safety valve, lower plenum, and fuel assemblies. Both short-term and long-term natural core cooling conditions are simulated and investigated using the RELAP5 code. Short-term analyses focus on the safety flapper valve operation and flow reversal mode. Long-term analyses include simulation of both complete SBO and long-term operation of the free convection mode. Results are promising for pool-type MTRs because this allows operators to investigate RELAP code abilities for MTR thermal–hydraulic simulations without any oscillation; moreover, the Tehran Research Reactor is conservatively safe against the complete SBO and long-term free convection operation.
机译：在本文中，在向下冷却的5 MW池式材料测试反应堆（MTR）中模拟并分析了整个电站的停电（SBO）或完全断电。该场景是在没有主动冷却系统和操作员的情况下进行的。代码节点化已成功地以反应堆运行参数的实验数据为基准。被动排热系统包括在重力作用下泵故障后进行的向下水冷却（冷却液向下流到滞留箱的未填充部分），安全挡板打开，从向下冷却方向到向上冷却方向的换向，然后整个挡板安全阀，下部增压室和燃料组件向上自由对流排热。短期和长期自然堆芯冷却条件都使用RELAP5代码进行了模拟和研究。短期分析的重点是安全挡板阀的操​​作和逆流模式。长期分析包括完整SBO的仿真和自由对流模式的长期运行。池型MTR的结果是有希望的，因为这使操作员能够在没有任何振荡的情况下研究MTR热工-液压模拟的RELAP代码能力。此外，德黑兰研究堆在整个SBO和长期自由对流操作方面具有保守的安全性。

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