高铀浓缩到低铀浓缩以来Triga Mark III核反应堆中子通量的变化

C. Vázquez-López, O. D. Ángel-Gómez, R. Raya-Arredondo, S. Cruz-Galindo, J. I. Golzarri-Moreno, Guillermo Espinosa
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引用次数: 1

摘要

利用核径迹探测器对Triga Mark III型研究堆的中子通量进行了研究。国家核研究所(ININ)的设施使用85 LEU 30/20(低浓缩铀)燃料元件的新堆芯负荷运行。该反应堆在辐照通道处提供约2 × 1012 n cm-2s-1的中子通量。在该通道中,CR-39(聚碳酸二烯丙基)兰道尔探测器暴露于中子中;探测器被3毫米的亚克力片覆盖,用于(n, p)反应。结果表明,在0.1 ~ 7kw范围内,反应堆功率与平均核径迹密度呈线性关系,数据重现性好,不确定度相对较低(±5%)。该方法是一种技术简单、快速、可靠的研究堆运行功率水平监测方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Changes of the Neutron Flux of the Nuclear Reactor Triga Mark III Since the Conversion from High to Low 235U Enrichment
The neutron flux of the Triga Mark III research reactor was studied using nuclear track detectors. The facility of the National Institute for Nuclear Research (ININ), operates with a new core load of 85 LEU 30/20 (Low Enriched Uranium) fuel elements. The reactor provides a neutron flux around 2 × 1012 n cm-2s-1 at the irradiation channel. In this channel, CR-39 (allyl diglycol policarbonate) Landauer® detectors were exposed to neutrons; the detectors were covered with a 3 mm acrylic sheet for (n, p) reaction. Results show a linear response between the reactor power in the range 0.1 - 7 kW, and the average nuclear track density with data reproducibility and relatively low uncertainty (±5%). The method is a simple technique, fast and reliable procedure to monitor the research reactor operating power levels.
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