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Investigation of Zr-Based Alloy Cladding Burst Mechanisms Under Station Blackout Using Bison

机译:野牛站停电对锆基合金熔覆破裂机理的研究

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Fuel rod behavior during accidents andtransients is one of the major safety issues for a lightwater reactor (LWR). As a result, fuel rod behavior underdesign basis accidents (DBA) such as loss of coolantaccident (LOCA) and reactivity initiated accident (RIA)has been extensively studied. After the Fukushima Daiichinuclear power plant accident, station blackout (SBO) hasbeen widely recognized as one of the most severepostulated events and the fuel rod behavior should be wellunderstood under such conditions. However, studies onfuel rod performance such as cladding failure under SBOare scarce. In this work, cladding burst mechanisms in ashort-term postulated SBO scenario without anymitigation measures have been investigated using theadvanced fuel performance code Bison developed atIdaho National Laboratory (INL). In particular, thesimulations were carried out for a full-length PWR fuelrod in which the cladding is Zry-4 with UO_2 fuel in a17x17 fuel assembly design. Four fuel rod burst criteriaare used in this comparative study: overstrain, plasticityinstability (PI), overstress (OS), and the combination ofOS/PI. It is found that all four rod burst criteria predictsimilar results in fuel rod failure time. As SBO starts afterreactor scram, fuel temperature drops rapidly. The fueltemperature reduces to about the same temperature as thatof the cladding for about 5000 seconds, and eventually thecladding and fuel temperatures increase quickly as thecoolant boils off. Meanwhile, significant fuel-claddingcontact is observed due to outward fuel thermal expansionand inward cladding creep resulting from higher externalpressure in the reactor primary system. The time to burstfor the cladding is about 6000 seconds, which is muchlonger than the typical few hundred seconds for a LOCAscenario. The fuel burst spot is in the high temperatureregion, accompanied by significant phase transformationfrom the hcp α-phase to the bcc β-phase around the burstzone. However, cladding ballooning is not observed underSBO, which is in contrast to the LOCA event. Therefore,the cladding burst mechanisms under SBO are apparentlydistinct from those under LOCA.
机译:事故和事故发生时油杆的行为 瞬态是灯的主要安全问题之一 水反应堆(LWR)。结果,在 设计基准事故(DBA),例如冷却液损失 事故(LOCA)和反应性引发事故(RIA) 已经被广泛研究。福岛第一核电站之后 核电站事故,车站停电(SBO)有 被广泛认为是最严重的事件之一 假定的事件和燃油杆行为应良好 在这样的条件下理解。但是,关于 SBO下的燃料棒性能,例如包层故障 稀缺。在这项工作中,熔覆机制 短期假设的SBO情景,没有任何 缓解措施已使用 Bison开发了先进的燃油性能代码 爱达荷州国家实验室(INL)。特别是 对全长压水堆燃料进行了模拟 包层为Zry-4且带有UO_2燃料的棒 17x17燃油组件设计。四个燃油棒爆破标准 在此比较研究中使用:过度应变,可塑性 不稳定(PI),过应力(OS)以及以下因素的组合 OS / PI。发现所有四个杆爆裂准则都可以预测 燃油杆故障时间的结果相似。随着SBO开始之后 反应堆急停后,燃料温度迅速下降。燃料 温度降低到与该温度大致相同的温度 大约5,000秒的熔覆层,最终 随着 冷却液沸腾。同时,大量的燃料包层 由于向外的燃料热膨胀,观察到接触 外部较高导致的向内包层蠕变 反应堆主系统中的压力。爆发的时间 包层大约需要6000秒 比LOCA的通常几百秒长 设想。燃油爆裂点处于高温 区域,伴随着明显的相变 从hcpα相到bccβ相 区。然而,在以下情况下未观察到覆层膨胀 SBO,与LOCA事件相反。所以, SBO下的熔覆破裂机制显然是 有别于LOCA。

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