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Extension of the Advanced Test Reactor Operating Envelope Via Enhanced Reactor Physics Validation Techniques

机译:通过增强的反应堆物理验证技术扩展高级测试堆的运行范围

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摘要

The Korea Atomic Energy Research Institute is currently in the process of qualifying a low-enriched-uranium fuel element design for the new Ki-Jang Research Reactor (KJRR). As part of this effort, a prototype KJRR fuel element was irradiated for several operating cycles in the northeast flux trap of the Advanced Test Reactor (ATR) at the Idaho National Laboratory. The KJRR fuel element contained a very large quantity of fissile material (618 g 235U) in comparison with historical ATR experiment standards (<1 g 235U), and its presence in the A TR flux trap was expected to create a neutronic configuration that would be well outside of the approved validation envelope for the reactor physics analysis methods used to support ATR operations.Accordingly, it was necessary to conduct an extensive set of new low-power physics measurements in the ATR Critical Facility (ATRC), a companion facility to the ATR, located in an immediately adjacent building and sharing the same fuel storage canal. The new measurements included fission power distributions, reactivity, and measurements related to the calibration of the in-core online instrumentation. The effort was focused on the objective of expanding the validation envelope for the computational reactor physics tools used to support ATR operations and safety analysis to include the planned KJRR irradiation in the ATR and similar experiments that are anticipated in the future.The computational and experimental results have demonstrated that the neutronic behavior of the KJRR fuel element in the ATRC is well understood in terms of its general effects on ATRC core reactivity and fission power distributions and its effects on the calibration of the ATR Lobe Power Calculation and Indication System, as well as in terms of its own internal fission rate distribution and total fission power per unit ATRC core power. Taken as a whole, these results have significantly extended the ATR physics validation envelope, thereby enabling an entire new class of irradiation experiments.
机译:韩国原子能研究所目前正在对新型Ki-Jang研究堆(KJRR)的低浓铀燃料元件设计进行鉴定。作为这项工作的一部分,在爱达荷州国家实验室的先进测试反应堆(ATR)的东北通量阱中,对KJRR原型燃料元件进行了几个操作循环的辐照。与历史上的ATR实验标准(<1 g 235U)相比,KJRR燃料元件包含大量的易裂变材料(618 g 235U),并且预期它在A TR通量阱中的存在会形成中子构型。远远超出了用于支持ATR操作的反应堆物理分析方法的批准验证范围之外。因此,有必要在ATR关键设施(ATRC)中进行一系列新的低功率物理测量,这是该设施的配套设施ATR,位于紧邻的建筑物中,并共享同一条燃料存储通道。新的测量包括裂变功率分布,反应性以及与核内在线仪器校准相关的测量。努力的重点是扩大用于支持ATR操作和安全性分析的计算反应堆物理工具的验证范围的目标,以将计划中的KJRR辐照包括在ATR中以及将来预期的类似实验中。已经证明,在ATRC中,KJRR燃料元件的中子行为对ATRC堆芯反应性和裂变功率分布的一般影响,以及对ATR叶片功率计算和指示系统的校准以及就其自身内部裂变率分布和单位ATRC核心功率的总裂变功率而言。总的来说,这些结果大大扩展了ATR物理验证范围,从而实现了全新的辐射实验类别。

著录项

  • 来源
    《Nuclear Technology》 |2018年第3期|228-246|共19页
  • 作者单位

    Idaho National Laboratory, Idaho Falls, Idaho;

    Idaho National Laboratory, Idaho Falls, Idaho;

    Idaho National Laboratory, Idaho Falls, Idaho;

  • 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

    Research reactors; experiments; physics;

    机译:研究堆;实验;物理学;

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