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Assessment of emergency core cooling system effectiveness for light water nuclear power reactors

机译:轻水核电反应堆应急堆芯冷却系统有效性评估

摘要

The effectiveness of Emergency Core Cooling Systems (ECCS) for light water nuclear power reactors was the subject of lengthy, controversial and technically complex hearings conducted by the AEC over the two years from 1971 through 1973. An independent, objective review and assessment of the technical issues associated with ECCS effectiveness was conducted in a study performed at the Environmental Quality Laboratory of the California Institute of Technology. The review was based upon the testimonies and supporting technical documentation of the principal participants in the hearings: the AEC, utilities, reactor manufacturers, and intervenors. ududFrom the review, the critical technical parameters influencing ECCS performance, which were at issue, are identified. Of fifteen parameters cited by the Advisory Committee on Reactor Safety in the hearings as being of unproved conservatism, essentially all are reviewed in detail, including, for example, the initial stored fuel energy, fuel rod gas gap conductance, fluid flow rates through broken pipes, metal-water reaction energy release and fuel rod embrittlement, reflood/core-spray heat transfer, and reflooding rates, as well as the adequacy of ECCS analytical models and numerical methods. ,The relative influence of uncertainties in the performance criteria associated with these parameters is assessed. Based upon the relative importance of these parameters, alternative responses to resolution of the ECCS problem are analyzed. The importance of the core reflooding rate in resolving the technical issues of the problem is emphasized. The conservatism of the proposed criteria (current and past) is reviewed. Recommendations are made for improvements in criteria conservatism, especially in the establishment of minimum reflood heat transfer rates (or alternatively, reflooding rates). Several new and/or accelerated research programs and additional large scale testing programs are also recommended. Suggestions are also made for areas in which design improvements would help to achieve greater ECCS reliability.
机译:AEC在1971年至1973年的两年间进行了冗长,有争议且技术复杂的听证会,主题是轻水核电反应堆应急堆芯冷却系统(ECCS)的有效性。对技术进行独立,客观的评估和评估在加州理工学院的环境质量实验室进行的一项研究中,进行了与ECCS有效性相关的问题。审查基于听证主要参加者的证词和辅助技术文件:AEC,公用事业,反应堆制造商和干预者。 ud ud通过审查,确定了影响ECCS性能的关键技术参数。反应堆安全咨询委员会在听证会上引用的15个参数未经证实是保守的,基本上所有这些参数都得到了详细审查,包括例如初始存储的燃料能量,燃料棒气隙电导率,通过破损管道的流体流速,金属-水反应能释放和燃料棒脆化,再驱/堆芯喷淋传热和再驱速率,以及ECCS分析模型和数值方法的充分性。 ,评估了与这些参数相关的性能标准中不确定性的相对影响。基于这些参数的相对重要性,分析了解决ECCS问题的替代响应。强调了核心回注率在解决问题的技术问题中的重要性。对所提议标准(当前和过去)的保守性进行了审查。建议改进标准的保守性,尤其是在建立最小再热传递速率(或再热率)的过程中。还推荐了几个新的和/或加速的研究程序以及其他大规模测试程序。还提出了一些领域的建议,在这些领域中,设计改进将有助于实现更高的ECCS可靠性。

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  • 作者

    Finlayson Fred C.;

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  • 年度 1975
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  • 原文格式 PDF
  • 正文语种 {"code":"en","name":"English","id":9}
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