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Study on shaft-block under small break loss of coolant accident of nuclear main pump

机译:核主泵冷却液小破损事故下轴瓦的研究

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To make sure that the reactor could be well protected under various accidents, hypotheses shall be made in design of the reactor to address possible accidents. Currently, the studies on shaft-block under small break loss of coolant accident (SBLOCA) are insufficient. This paper could provide more reference to this field. Firstly, external characteristics before and after the shaft-block accident under SBLOCA are obtained through experiments. Then, computational fluid dynamics (CFD) analysis is used to analyze the change of inner flow and the interaction between SBLOCA and shaft-block accident of the nuclear main pump. This paper shows that after the shaft-block accident happens, the speed of the main pump is reduced to zero quickly, while the disappearance of the flow takes a longer time. While the impellers are slowing down, different parts in the blades lose the ability to transfer energy to the fluid one after another, which in external characteristic is demonstrated with the head and torque reducing to negative values successively. Relatively significant change in the inner flow field of the pump happened in the shaft-block process, and clear regular change pattern could be found in rotor and stator blade interaction. The impact of SBLOCA on the shaft-block accident of the nuclear main pump is mainly on the external characteristic changes in the early stage of the accident, and the higher the extent of SBLOCA is, the more significant the impact will be. (C) 2019 Elsevier Ltd. All rights reserved.
机译:为确保反应堆在各种事故下得到良好的保护,应在反应堆的设计中做出假设以解决可能发生的事故。目前,关于冷却液小断裂损失事故下轴瓦的研究还不够。本文可以为该领域提供更多参考。首先,通过实验获得了SBLOCA下竖井堵块事故前后的外部特征。然后,使用计算流体动力学(CFD)分析来分析内部流量的变化以及SBLOCA与核主泵轴块事故之间的相互作用。本文表明,在发生轴封事故后,主泵的速度迅速降至零,而流量消失则需要更长的时间。当叶轮减速时,叶片中的不同部分会失去将能量一次又一次地传递给流体的能力,这在外部特性上得到了证明,扬程和扭矩相继降低至负值。泵的内部流场在轴块过程中发生了相对较大的变化,并且在转子和定子叶片的相互作用中可以找到清晰的规律变化模式。 SBLOCA对核主泵轴瓦事故的影响主要在于事故早期的外部特性变化,SBLOCA的程度越高,影响将越大。 (C)2019 Elsevier Ltd.保留所有权利。

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