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Stress-testing the ALFRED design - Part III: Safety margins evaluation

机译:对ALFRED设计进行压力测试-第三部分:安全裕度评估

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摘要

The advancement of the design of the Advanced Lead-cooled Fast Reactor European Demonstrator (ALFRED) beyond the conceptual phase, passes through the analysis of the impact of uncertainties, notably to what concerns safety-related conditions. Compliancy of plant safety to Design Extension Conditions is, according to IAEA and in line with the meaning itself of these beyond-design conditions, usually investigated by best estimates only. Due however to the demonstration nature of ALFRED, it was decided to assess the actual safety performances of this system even in ultimate conditions. To this regard, the emphasis was put on unprotected events like the UTOP (unprotected transient of over-power) and ULOOP (unprotected loss of offsite power, resulting from the combination of a loss of flow and loss of heat sink under unprotected conditions), pinpointed as the most challenging situations sought for the plant. The purpose of the present work, which has been divided in three parts, was then to assess the ultimate ALFRED safety margins against failure of the key core components and systems (Part III). To target this objective, the evaluation of uncertainties coming, on one hand, from nuclear data was performed at first, to retrieve their impact on the reactivity coefficients, thereby on the transient behavior driven by the latter (Part I); then, uncertainties from material properties, fabrication procedures, operation and measurement, and computational tools were propagated to assess their influence on the thermal hydraulics of the system (Part II). In this work the efforts of Parts I and II are merged together and the effect of uncertainties on safety margins and salient parameters assessed. The retrieved uncertainties are propagated to the expected number of pins experiencing fuel melting during an UTOP and to the clad time-to-failure during an ULOOP. The former has been found to be quite affected by uncertainties, but still under limits not directly posing hazards to the people and the environment, even when extremely conservative assumptions are put forward; the latter shows a milder response to uncertainties, but always guaranteeing more than an order of magnitude of safety margin relative to WENRA recommendations.
机译:欧洲领先的铅冷快堆欧洲演示器(ALFRED)的设计超越了概念阶段,它通过对不确定性的影响进行了分析,尤其是对与安全相关的条件的影响。根据国际原子能机构的说法,工厂安全符合设计延展条件是符合这些超设计条件本身的含义的,通常仅根据最佳估计进行调查。但是,由于ALFRED具有演示性,因此决定即使在最终条件下也要评估该系统的实际安全性能。在这方面,重点放在未受保护的事件上,例如UTOP(未受保护的过功率瞬变)和ULOOP(受保护的情况下,由于流量损失和散热片的损失而导致的非保护性场外功率损失),被确定为该工厂寻求的最具挑战性的情况。然后,本工作分为三个部分,目的是评估针对关键核心组件和系统出现故障的最终ALFRED安全裕度(第三部分)。为了实现这一目标,首先对核数据的不确定性进行了评估,以求取其对反应系数的影响,从而对反应系数的瞬态行为产生影响(第一部分)。然后,传播了来自材料特性,制造程序,操作和测量以及计算工具的不确定性,以评估它们对系统热液压的影响(第二部分)。在这项工作中,将第一部分和第二部分的工作合并在一起,并评估了不确定性对安全裕度和突出参数的影响。检索到的不确定性会传播到UTOP期间经历燃料熔化的销的预期数量,以及ULOOP期间发生故障的复合时间。已经发现前者受到不确定性的很大影响,但是即使提出了非常保守的假设,前者仍然不受直接危害人类和环境的限制;后者显示出对不确定性的温和响应,但相对于WENRA建议,始终保证超过一个数量级的安全裕度。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2018年第7期|433-439|共7页
  • 作者

    Lodi F.; Grasso G.;

  • 作者单位

    UniBO Univ Bologna, DIN Lab Montecuccolino, Via Colli 16, I-40136 Bologna, Italy;

    ENEA Italian Natl Agcy New Technol Energy & Susta, Via Martini di Monte Sole 4, I-40129 Bologna, Italy;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    ALFRED; Safety analysis; Transients; Uncertainty analysis; Fast reactors;

    机译:ALFRED;安全分析;瞬态;不确定性分析;快速反应堆;

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