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Longitudinal deformation study of pressure tube of Indian PHWR under high temperature transient
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2021-02-05 , DOI: 10.1016/j.anucene.2021.108160
Ankit R. Singh , Andallib Tariq , Pradeep K. Sahoo , Prasanna Majumdar , Deb Mukhopadhyay

Moderator acts as primary heat sink to arrest the unwarranted heat-up of fuel channels in the scenario of loss of coolant accident along with the unavailability of emergency core cooling system. In addition, severe heat-up of channel (which consists of fuel bundles, Pressure Tube, PT and Calandria Tube, CT) also occurs during any un-called for event of moderator-cooling/make-up system malfunctioning. Eventually, this all lead to the major loss in structural rigidity. Present investigation is performed to study the sagging deformation of PT for standardized 220MWe Indian PHWR. A scaled-down PT (1/3rd scale) is tested with a uniquely designed experimental setup that is capable of capturing high temperature sagging behavior. Results confirm that the Indian PT significantly deforms under thermally assisted rate-dependent plasticity (creep) above 600 °C. Post-test visual examination reveals no cracks in the PT, however a significant thinning of the PT near the junction of weight simulators is observed.



中文翻译:

高温瞬变下印度PHWR压力管的纵向变形研究

主持人充当主要散热器,以在发生冷却剂意外事故以及没有应急核心冷却系统的情况下,阻止燃料通道不必要的升温。此外,在减速器/补给系统发生故障的任何非要求事件中,还会严重地加热通道(由燃料束,压力管,PT和Calandria管组成)。最终,所有这些都会导致结构刚度的重大损失。目前进行的研究是为了研究标准220MWe印度PHWR PT的下垂变形。比例缩小的PT(1/3比例)已通过独特设计的实验设置进行了测试,该设置能够捕获高温下垂行为。结果证实,印度PT在高于600°C的热辅助速率依赖性塑性(蠕变)下会明显变形。测试后的目视检查未发现PT出现裂纹,但是在重量模拟器的交界处发现PT明显变薄。

更新日期:2021-02-05
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