首页> 外文会议>International topical meeting on high temperature reactor technology;HTR 2008 >SENSITIVITY STUDY ON DEPRESSURIZED LOFC ACCIDENTS WITH A FAILURE OF THE RCCS IN A MODULAR GAS-COOLED REACTOR
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SENSITIVITY STUDY ON DEPRESSURIZED LOFC ACCIDENTS WITH A FAILURE OF THE RCCS IN A MODULAR GAS-COOLED REACTOR

机译:模块化气冷堆中RCCS失效的减压LOFC事故的敏感性研究

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A modular gas-cooled reactor design with a thermal output of 600MWt and a core exit temperature of 950°C has been designed by the Korea Atomic Energy Research Institute based on the GT-MHR reactor concept which adopts a prismatic core. A sensitivity study on the transient plant behavior during a postulated depressurized LOFC accident concurrent with the failure of the RCCS was performed. In the transient analysis, the GAMMA+ code which can handle multi-dimensional, multi-component problem was used. The RCCS is a passive system which is very reliable and supplies a significant heat removal mechanism during abnormal conditions in a GCR. To investigate the safety characteristics of a GCR under the one of the worst accidental scenarios, a simultaneous failure of the RCCS with a depressurized LOFC was assumed. The thermal behavior of the reactor system was analyzed in various conditions. It is found that the maximum temperature of the reactor fuel compact could exceed 1600°C at about 50 hours at the condition of a depressurized LOFC with a failure of the RCCS. A problem with the structural integrity of the reactor pressure vessel could also be a critical factor. The insulation of a reactor cavity wall serves as a dominant obstacle against a heat transfer from the reactor vessel to the surrounding ground when the RCCS fails to operate. Without insulation material on the reactor cavity wall, the gradients of the increasing rate of the maximum temperature diminish and the peak values decrease. The maximum temperatures of the fuel compact and the reactor vessel are less sensitive to the concrete and surrounding soil properties, those are the thermal conductivity and volumetric heat capacity, when the insulation material is used. Theuncertainties in the properties of the concrete and the surrounding soil become significant without an insulation material in the cavity. To improve the safety of a modular GCR, more effective and feasible heat removal mechanism need to be devised based on the comprehensions on the heat transfer characteristics.
机译:韩国原子能研究院根据GT-MHR反应堆概念设计了模块化的气冷堆设计,其热输出功率为600MWt,堆芯出口温度为950°C,采用棱柱形堆芯。进行了对假定的低压LOFC事故和RCCS失效期间的瞬时植物行为的敏感性研究。在瞬态分析中,使用了可以处理多维,多组件问题的GAMMA +代码。 RCCS是一种非常可靠的无源系统,在GCR中出现异常情况时,它可以提供重要的散热机制。为了研究最严重的意外情况之一下的GCR的安全特性,假设RCCS伴随LOFC降压而同时失效。在各种条件下分析了反应器系统的热行为。发现在减压的LOFC和RCCS失效的情况下,反应堆燃料压块的最高温度在约50小时时可超过1600℃。反应堆压力容器的结构完整性问题也可能是一个关键因素。当RCCS无法运行时,反应堆空腔壁的隔热层是阻止热量从反应堆容器传递到周围地面的主要​​障碍。在反应器腔壁上没有绝缘材料的情况下,最高温度的上升速率的梯度减小,并且峰值减小。当使用绝缘材料时,燃料压块和反应堆容器的最高温度对混凝土和周围的土壤特性不太敏感,这些特性是热导率和体积热容。这 在型腔中没有绝缘材料的情况下,混凝土和周围土壤的性能不确定性变得很明显。为了提高模块化GCR的安全性,需要根据对传热特性的理解,设计出更有效,可行的排热机构。

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