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CPR1000核电厂地坑滤网潜在堵塞问题解决方案研究及工程实施

发布时间:2018-11-24 13:37
【摘要】:核电厂安全壳地坑滤网潜在堵塞问题长期以来一直是国际核工业界重点关注的核安全问题。传统设计中,假设安全壳地坑滤网堵塞率小于50%,这一假设是不保守的,存在重大核安全风险。根据NRC技术导则要求,对核电厂的相关事故情景进行分析,确定最保守的工况及该工况下的系统工艺参数,作为后续分析工作的输入数据。对电厂的相关设计资料进行收集,开展现场踏勘核实电厂实际状态与图纸状态的一致性。根据输运到地坑滤网的碎片数量最大或输运到地坑滤网的碎片组合最坏的原则,选择可能存在的5种保守破口类型,并针对最保守的破口工况开展碎片生成分析。对于不同类型的保温碎片还需确认ZOI(Zone Of Influenced)及其形状和大小,最终得到事故后生产碎片的数量和性质。根据碎片生成分析结果,参照NEI-04-07导则,进行了碎片的输运分析。碎片输运主要考虑喷放输运、喷淋冲洗输运、地坑充水输运和再循环输运四种类型。通过采用逻辑树和精细分析两种分析方法,分别计算传输到地坑滤网的各种碎片的输运份额,从而得到两种计算方法下输运到地坑滤网的碎片总量。结合电厂已有的数据输入,进行地坑滤网容量计算,并对所采购的地坑滤网进行了设备试验鉴定。采用常温下多组试验条件进行试验,利用温度修正法得出事故后120℃工况下的地坑滤网压损。本文总结CPR1000核电厂安全壳地坑滤网潜在失效问题的研究经验和主要技术结论。参考美国率先开展的安全壳地坑滤网潜在堵塞问题研究成果,以美国NRC相关规定和技术导则为依据,对CPR1000核电厂的地坑滤网潜在堵塞问题进行了全面、系统的分析和评估,提出了地坑滤网潜在堵塞问题的解决方案,并在CPR1000核电工程上进行了实施,有效解决了地坑滤网潜在堵塞问题,消除了相关的核安全风险。
[Abstract]:The potential clogging of containment pit filters in nuclear power plants has long been a nuclear safety problem focused on by the international nuclear industry. In the traditional design, the assumption that the clogging rate of containment pit filter is less than 50 is not conservative, and there are significant nuclear safety risks. According to the requirements of NRC technical guidelines, the relevant accident scenarios of the nuclear power plant are analyzed, and the most conservative operating conditions and the system process parameters under the condition are determined as the input data for the subsequent analysis. Collect relevant design data of power plant and carry out site survey to verify the consistency between actual status and drawing state of power plant. According to the principle of the maximum number of fragments transported to the ground pit filter or the worst combination of the fragments transported to the ground pit filter, five possible conservative break types are selected, and the debris generation analysis is carried out for the most conservative break condition. For different types of thermal insulation debris, ZOI (Zone Of Influenced) and its shape and size should be confirmed, and the quantity and properties of the fragments produced after the accident can be obtained. According to the results of debris generation analysis and NEI-04-07 guidelines, the transport of fragments was analyzed. Debris transport mainly includes spray transport, spray flushing transport, pit filling transport and recycle transport. By using the logical tree and fine analysis methods, the transport shares of various fragments transferred to the ground pit filter net are calculated, respectively, and the total amount of debris transported to the ground pit filter net is obtained under the two calculation methods. Combined with the existing data input of the power plant, the capacity of the ground pit filter was calculated, and the equipment test and appraisal of the purchased ground pit filter were carried out. The pressure loss of the filter net at 120 鈩,

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