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PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code

机译:使用BISON燃料性能代码在LWR稳态和反应堆启动操作下对Zircaloy涂层复合材料进行PCI分析

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摘要

Research following the earthquake and subsequent tsunami that devastated the Fukushima Daiichi nuclear power plant, causing severe damage to the reactor cores, has led to the development of accident tolerant fuel designs. Accident tolerant fuels are described as a fuel form which exhibits improved material response, when compared to traditional uranium dioxide fuel clad by a zirconium alloy, during accident (e.g., loss of coolant accident or reactivity insertion accident) while maintaining or exceeding normal reactor operational expectations. One of the primary goals of accident tolerant fuel concepts is to reduce cladding corrosion by either replacing traditional Zircaloy cladding with a new material or by applying a coating to the outer surface of the cladding with enhanced resistance to corrosion at high temperatures. However, while coating the clad may provide an increase in high temperature corrosion resistance, it also changes the mechanical state of the cladding and potentially creates alternate failure mechanisms during reactor operations or accident conditions. This research has primarily focused on the pellet-cladding interactionmechanical response of FeCrAl (Iron-Chromium-Aluminum alloy) coated cladding during light water reactor steady state and reactor startup operations. Using the MOOSE-based, finite-element fuel performance code BISON and commercial pressurized water reactor data obtained from Diablo Canyon Unit 2, a preliminary analysis was performed to evaluate the performance of FeCrAl coated cladding under steady state operation and its mechanical stability under pellet-cladding interaction during a reactor startup. This work summarizes BISON 2-D radial-axially symmetric (R-Z) and radial-circumferentially symmetric (R-theta) simulation results by comparing 20, 50, and 100-mu m FeCrAl coating thicknesses as well as FeCrAl cladding to traditional Zr-4 cladding under pellet-cladding interaction condition. The results of this study will provide a feasibility analysis for steady state and transient operational response of FeCrAl coated, Zircaloy cladding. Furthermore, this work will provide a fundamental basis for the assessment of the ability of coated cladding, as an ATF candidate, to maintain or exceed current steady state reactor operating expectations.
机译:地震和随后的海啸摧毁了福岛第一核电站,造成了对反应堆堆芯的严重破坏,这项研究导致了事故容忍燃料设计的发展。事故容忍燃料被描述为一种燃料形式,与锆合金包覆的传统二氧化铀燃料相比,在事故发生期间(例如,冷却液损失事故或反应性插入事故),同时保持或超过了正常的反应堆运行预期。事故容忍性燃料概念的主要目标之一是通过用新材料代替传统的Zircaloy包壳或通过在包壳的外表面涂覆具有增强的耐高温腐蚀性能的涂层来减少包壳腐蚀。然而,尽管涂覆包层可以提供提高的耐高温腐蚀性能,但它也改变了包层的机械状态,并可能在反应堆运行或事故情况期间产生替代的失效机理。这项研究主要集中在轻水反应堆稳定状态和反应堆启动运行期间,FeCrAl(铁-铬-铝合金)包覆的覆层的颗粒-覆层相互作用机理。使用基于MOOSE的有限元燃料性能代码BISON和从Diablo Canyon Unit 2获得的商业压水堆数据,进行了初步分析,以评估稳态运行下FeCrAl涂层熔覆层的性能及其在颗粒下的机械稳定性。反应堆启动过程中的包层相互作用。这项工作通过比较20、50和100微米的FeCrAl涂层厚度以及FeCrAl覆层与传统Zr-4的厚度,总结了BISON二维径向轴向对称(RZ)和径向周向对称(R-theta)仿真结果颗粒-包层相互作用条件下的包层。这项研究的结果将为FeCrAl涂层Zircaloy覆层的稳态和瞬态运行响应提供可行性分析。此外,这项工作将为评估作为ATF候选涂层的包层保持或超过当前稳态反应堆的运行预期的能力提供基础。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2018年第6期|383-391|共9页
  • 作者单位

    Struct Integr Associates, 5435 Oberlin Dr, San Diego, CA 92121 USA;

    Struct Integr Associates, 5435 Oberlin Dr, San Diego, CA 92121 USA;

    Struct Integr Associates, 5435 Oberlin Dr, San Diego, CA 92121 USA;

    Struct Integr Associates, 5435 Oberlin Dr, San Diego, CA 92121 USA;

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

  • 入库时间 2022-08-18 00:40:46

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