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U.S. DOE SEVERE ACCIDENT RESEARCH FOLLOWING THE FUKUSHIMA DAIICHI ACCIDENTS

机译:继福岛大地事故后的美国能源部重大事故研究

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The Department of Energy (DOE) has played a major role in the US response to the events at Fukushima Daiichi. During the first several weeks following the accident, US assistance efforts were guided by results from a significant and diverse set of analyses. In the months that followed, a coordinated analysis activity aimed at gaining a more thorough understanding of the accident sequence was completed using laboratory-developed system-level and best-estimate accident analysis codes, while a parallel analysis was conducted by industry. A comparison of predictions for Unit 1 from these two studies indicated significant differences between MAAP and MELCOR results for key plant parameters, such as in-core hydrogen production. On that basis, a cross-walk was completed to determine the key modeling variations that led to these differences. In parallel with these activities, it became clear that there was a need to perform a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of LWR severe accident research, and augmented by insights from Fukushima. In addition, there is growing international recognition that data from Fukushima could significantly reduce uncertainties related to severe accident progression, particularly for BWRs. On these bases, a group of US experts in LWR safety and plant operations was convened by the DOE office of Nuclear Energy (DOE-NE) to complete technology gap analysis and Fukushima forensics data identification activities. Results from these activities were used as the basis for refining DOE-NE's severe accident Research and Development (R&D) plan. This paper provides a high-level review of DOE sponsored R&D efforts in these areas, including planned activities on accident tolerant components and accident analysis methods.
机译:能源部(DOE)在美国对福岛第一核电站事件的反应中发挥了重要作用。事故发生后的前几周,美国的援助工作以一系列重要而多样的分析结果为指导。在随后的几个月中,使用实验室开发的系统级和最佳估计的事故分析代码完成了旨在更全面地了解事故序列的协调分析活动,而行业进行了并行分析。两项研究对1号机组的预测结果进行了比较,结果表明MAAP和MELCOR结果在关键工厂参数(如核心氢生产)之间存在显着差异。在此基础上,完成了人行横道以确定导致这些差异的关键建模变量。在开展这些活动的同时,很明显,有必要对事故容忍组件和严重事故分析方法进行技术差距评估,目的是在给定当前状况的情况下,确定可能存在的任何数据和/或知识差距。 LWR严重事故研究,并得到了福岛的见解。此外,国际上越来越认识到,福岛的数据可以大大减少与严重事故进展有关的不确定性,特别是对于压水堆。在这些基础上,美国能源部核能办公室(DOE-NE)召集了一组有关轻水堆安全和工厂运营的美国专家,以完成技术差距分析和福岛法医数据识别活动。这些活动的结果被用作完善DOE-NE严重事故研究与开发(R&D)计划的基础。本文对DOE赞助的这些领域的研发工作进行了高级别的回顾,包括计划中的事故容忍组成部分活动和事故分析方法。

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