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DEVELOPMENT OF CRITICALITY RISK EVALUATION METHOD FOR FUEL DEBRIS IN FUKUSHIMA DAI-ICHI NPS

机译:福岛第一核电站核燃料碎片危险性评估方法的发展

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After the accident of Fukushima Dai-ichi Nuclear Power Station, there has been still damaged nuclear fuel in the reactor buildings, which is called "fuel debris" and contains an amount of fissile materials more than the minimum criticality amount. Measured data of Xe gas show that it is currently subcritical, which must be kept until finishing retrieval work. In the latest plan, retrieving fuel debris is to start in 2025. The International Research Institute for Nuclear Decommissioning, IRID, has been developing the technology for decontamination in reactor building. A developed method will be reviewed and granted by the Nuclear Regulatory Authority in Japan, NRA, before the start of the retrieving. Criticality risk information will be needed for decision making on following two subcriticality issues, -Criticality control of fuel debris to keep it subcritical until the end of retrieval work. -Safe operation for retrieving fuel debris to keep it subcritical. Because fuel debris has been out of criticality control and the key condition for its current subcriticality is unknown, it is important to obtain criticality risk information as soon as possible. Applying conventional Probabilistic Safety Assessment, PSA, to fuel debris is difficult, because it is based on the probability of becoming out of criticality control due to troubles such as equipment failure, operation mistake and so on. A new method, which has been developed by Japan Atomic Energy Agency to technically support the NRA, is designed to estimate criticality risk based on a probability distribution of k_(eff) due to uncertainty of composition and geometry of fuel debris, which method will provide risk information for the two subcriticality issues as well as for the tolerance level of criticality risk if it is unavoidable. Developed method contains four steps: two steps of analysis of criticality risk and two steps of quantification of the risk. A procedure of risk quantification has been defined, in which systematic analysis of criticality risk can be done by making "status matrix." A trial analysis by using the procedure shows that some events which can initiate criticality are able to be supposed to happen during maintenance period until the beginning of retrieving fuel debris, and that analysis also indicates countermeasures should be considered as soon as possible in order to reduce criticality risk for public and workers.
机译:福岛第一核电站事故发生后,反应堆建筑物中仍然有损坏的核燃料,被称为“燃料碎片”,其裂变材料的数量超过了最低临界数量。氙气的实测数据表明,它目前处于亚临界状态,必须保留直到完成检索工作为止。在最新计划中,回收燃料碎片的工作将于2025年开始。国际核退役研究所(IRID)一直在开发反应堆制造中的去污技术。在检索开始之前,日本核监管局NRA将审查并批准一种已开发的方法。对于以下两个次临界问题,决策将需要临界风险信息:-燃料碎片的临界控制,以使其处于次临界状态,直到检索工作结束。 -安全操作,可回收燃料碎屑以保持其次临界状态。由于燃料碎片已经超出关键性控制并且其当前次关键性的关键条件未知,因此尽快获取关键性风险信息非常重要。将常规的概率安全评估PSA应用于燃料残渣是困难的,因为它基于设备故障,操作失误等问题而导致无法进行关键性控制的可能性。日本原子能机构开发了一种新方法来为NRA提供技术支持,该方法旨在基于k_(eff)的概率分布(由于燃料碎片的成分和几何形状的不确定性)来估计临界风险,该方法将提供两个亚临界问题的风险信息,以及不可避免的临界风险的承受水平。所开发的方法包括四个步骤:分析关键风险的两个步骤和量化风险的两个步骤。已经定义了风险量化程序,其中可以通过制作“状态矩阵”来对关键风险进行系统分析。通过使用该程序进行的试验分析表明,在维护期间直至开始回收燃料残渣之前,可能会引发一些可能导致严重事故的事件,并且该分析还表明,应尽快考虑采取对策,以减少事故的发生。对公众和工人的危害性风险。

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