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

机译:福岛Daiichi事故后,美国Doe严重事故研究

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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)在美国对福岛达义的活动的回应中发挥了重要作用。在事故发生后的前几周,美国援助努力是由一系列重要和多样化的分析的结果指导。在随后的几个月内,使用实验室开发的系统级和最佳估计事故分析代码完成了旨在获得对事故序列更彻底了解的协调分析活动,同时由行业进行平行分析。从这两种研究的单元1预测的比较表明了MAAP与熔体结果之间的显着差异,用于关键植物参数,例如核心氢气产生。在此基础上,完成交叉步行以确定导致这些差异的关键建模变化。与这些活动并行,很明显,需要对事故耐受组件和严重事故分析方法进行技术差距评估,其目的是鉴定当前状态可能存在的任何数据和/或知识差距LWR严重事故研究,并通过福岛的见解来增强。此外,日益增长的国际认可,来自福岛的数据可以显着减少与严重事故进展相关的不确定性,特别是对于BWRS。在这些基础上,由核能(DOE-NE)的DOE办公室召集了一群美国的美国专家,以完成技术差距分析和福岛取证数据识别活动。这些活动的结果被用作炼制DOE-NE严重事故研究和开发(研发)计划的基础。本文对这些领域的DOE赞助研发努力提供了一个高级别的审查,包括有关事故耐受组件和事故分析方法的计划活动。

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