Changes of the Neutron Flux of the Nuclear Reactor Triga Mark III Since the Conversion from High to Low 235U Enrichment

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

Abstract

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.
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
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。
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