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首页> 外文期刊>Journal of nuclear science and technology >BWR Loss of Coolant Integral Tests with Two Bundle Loop, (I)Thermal-Hydraulic Characteristics in Parallel Channels
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BWR Loss of Coolant Integral Tests with Two Bundle Loop, (I)Thermal-Hydraulic Characteristics in Parallel Channels

机译:具有两个束流回路的冷却液整体测试的BWR损失,(I)平行通道中的热工-液压特性

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摘要

Two simulation tests of a BWR loss-of-coolant accident (LOCA) by a postulated guillotine rupture of a recirculation suction line were conducted using the Two Bundle Loop (TBL), which was volumetrically scaled to a BWR/5 plant with 764 fuel bundles. The major objective of the tests was to clarify thermal-hydraulic difference in parallel bundles. In the tests, the failure of a diesel generator for two low pressure coolant injection (LPCI) pumps was as-sumed, and the initial bundle power combinations were 4.0 and 5.9 MW in the first test, and 5.0 and 4.9 MW in the second.In one of the two bundles, the rods heated up locally in the radial direction. In the other, the rods heated up rather uniformly and later than in the former bundle. Much water fell locally into the former bundle, while ascending steam flow from the lower plenum was larger in the latter. A difference in thermal-hydraulic responses was observed even in the case of nearly identical bundle powers, but the difference was less than in the case of dif-ferent bundle powers. The peak cladding temperatures in the tests were lower L han 704 K.
机译:通过使用两束环(TBL)对假定的循环吸油管断头台破裂造成的BWR冷却液失水事故(LOCA)进行了两项模拟测试,该体积按比例缩放为具有764个燃料束的BWR / 5工厂。测试的主要目的是弄清平行束中的热工水力差异。在测试中,假定了两个低压冷却剂注入(LPCI)泵的柴油发电机故障,第一次测试的初始束功率组合为4.0和5.9 MW,第二次测试为5.0和4.9 MW。在两个束中的一个束中,杆在径向上局部加热。在另一种情况下,棒的加热相当均匀,并且比前一捆中的要晚。大量的水局部滴入前一束,而来自下增压室的上升蒸汽流量更大。即使在束功率几乎相同的情况下,也观察到热工水力响应的差异,但该差异小于束功率不同的情况。测试中的最高包层温度低于704 K L.

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