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The Amount of Hydrogen Generation andRadionuclides Release during SevereAccidents of a Pressurized Water Reactor

机译:压水堆严重事故中的氢气产生量和放射性核素释放量

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The need for a methodology to assess thedegree of core damage was part of the U.S. NuclearRegulatory Commission's change in licensing andoperation requirements after the Three Mile Islandaccident. Core damage assessment is used by theemergency response organization to determine theappropriate Emergency Action Levels (EALs), toselect the source term for estimation the offsite dose,to predict the radiation protection actions that shouldbe considered for long term recovery activities. In theCore Damage Assessment Guidance (CDAG)documented in WCAP-14696 report, WestinghouseOwners Group suggested that the containmentradiation level and hydrogen concentration in thecontainment together with some other existinginstrumentation, e.g. core exit thermocouples, reactorwater level, can be used to determine the degree ofcore damage.It is well known that the amount radionuclidesreleased from the fuel, retained in the reactor coolantsystem (RCS), and its distribution amongcontainment compartments depend on the accidentsequence. The amount of hydrogen generation andthe containment hydrogen concentration are alsosequences dependent. In the present analysis, asystematic MAAP calculation is performed toinvestigate the impact of accident scenarios on theamount of radionuclides and hydrogen concentrationin the containment. The purpose of the study is tosupport the developed of the plant specific CADG.Eleven sequences are analyzed in the presentstudy. The sequences analyzed included loss coolant accidents (several breach sizes and locations) andstation blackout sequence. Various mitigation actionsare considered in the calculations to study the impactof these actions on the containment radiation leveland hydrogen concentration. The major resultsdiscussed in the paper include: fractional release ofradionuclides from the fuel pellets, retention factor ofradionuclides within RCS, oxidation fraction ofcladding, retention factor of hydrogen within RCS,possibility of hydrogen combustion.
机译:三核岛事故发生后,美国核监管委员会对许可和运营要求进行更改的一部分是需要一种评估核心损坏程度的方法的方法。应急响应组织使用核心损害评估来确定适当的紧急行动级别(EAL),选择用于估算异地剂量的源术语,以预测长期恢复活动应考虑的辐射防护措施。在WCAP-14696报告中记录的《核心损害评估指南》(CDAG)中,西屋所有者组织建议该容器中的安全壳辐射水平和氢浓度以及其他一些现有的仪器,例如堆芯出口热电偶,反应堆水位可用于确定堆芯损坏的程度。众所周知,从燃料释放的,保留在反应堆冷却剂系统(RCS)中的放射性核素的数量及其在安全壳之间的分布取决于事故的发生顺序。氢气的产生量和安全壳氢气浓度也取决于序列。在本分析中,进行了系统的MAAP计算,以研究事故情景对安全壳中放射性核素含量和氢浓度的影响。本研究的目的是支持植物特异性CADG的开发。本研究分析了11个序列。分析的顺序包括冷却液损失事故(几个违规尺寸和位置)和停电顺序。计算中考虑了各种缓解措施,以研究这些措施对安全壳辐射能级和氢浓度的影响。本文讨论的主要结果包括:燃料颗粒中放射性核素的部分释放,RCS中放射性核素的保留因子,包层的氧化分数,RCS中氢的保留因子,氢燃烧的可能性。

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