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Experimental investigation of stratified two-phase flows in the hot leg of a PWR for CFD validation

机译:用于CFD验证的压水堆热段中分层两相流的实验研究

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In the event of hypothetical accident scenarios in a pressurised water reactor (PWR), emergency strategies have to be mapped out, in order to guarantee the reliable removal of the decay heat from the reactor core, also in case of component breakdown. Therefore, the primary circuit is designed to favour a natural circulation which allows releasing the heat to the secondary circuit over the steam generators (SG). One of the most important passive heat removal mechanisms is the reflux cooling mode, which can be operated as long as the secondary side of the steam generators is filled with water. In the reflux condenser mode [19], the water level in the reactor pressure vessel (RPV) is already reduced to the level of the hot leg nozzle or even below, consequently, only steam flows to the steam generator. The steam arriving from the RPV condenses in the vertical U-tubes of the steam generator and, in each half of the steam generator, the condensate flows down the tube in which it has been formed. Therefore, about one half of the condensate flows as usual over the pump to the downcomer, whereas the other part flows over the hot leg back to the upper plenum. In the hot leg, the condensate has to flow in counter-current to the steam. However, the stratified counter-current flow of condensate and steam is only stable for a certain range of flow rates [1]. In fact, if the steam flow increases too much, the condensate is clogged in the hot leg. This is the onset of the counter-current flow limitation (CCFL): the liquid is carried over by the steam and partially entrained in opposite direction to the steam generator. As a consequence, the hot leg and steam generator are flooded, which decreases the water level in the RPV and reduces core cooling. In case of an additional increase of the steam flow, the condensate is completely blocked and the reflux cooling mode ends. In this situation, cooling of the reactor core from the hot leg is impossible, but may be continued by coolant drained through the cold leg to the downcomer.
机译:在压水堆(PWR)中发生假想的事故情况时,必须制定应急策略,以确保在组件发生故障的情况下也能可靠地从反应堆堆芯中除去衰变热。因此,主回路设计成有利于自然循环,从而允许热量通过蒸汽发生器(SG)释放到副回路。最重要的被动除热机制之一是回流冷却模式,只要蒸汽发生器的次级侧充满水,就可以运行该模式。在回流冷凝器模式[19]中,反应堆压力容器(RPV)中的水位已降至热腿喷嘴的水位,甚至更低,因此,只有蒸汽流向蒸汽发生器。从RPV到达的蒸汽在蒸汽发生器的垂直U型管中冷凝,并且在蒸汽发生器的每一半中,冷凝液向下流向已形成冷凝器的管。因此,大约一半的冷凝液像往常一样通过泵流向降液管,而另一部分冷凝液则通过热管流回到上增压室。在热段中,冷凝水必须与蒸汽逆流流动。但是,冷凝水和蒸汽的分层逆流仅在一定范围的流量下才稳定[1]。实际上,如果蒸汽流量增加太多,冷凝水就会在热管中堵塞。这是逆流限制(CCFL)的开始:液体被蒸汽带走,并在与蒸汽发生器相反的方向上被部分夹带。结果,热段和蒸汽发生器被淹没,这降低了RPV中的水位并减少了堆芯冷却。在蒸汽流量进一步增加的情况下,冷凝水被完全堵塞,回流冷却模式结束。在这种情况下,不可能从热段冷却反应堆堆芯,但可以通过从冷段排放到降液管的冷却剂继续冷却。

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