首页> 外文期刊>Journal of nuclear science and technology >Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
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Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel

机译:高浓缩铀或中浓缩铀燃料负载轻水缓和重水反射圆柱核反应温度系数的实验研究

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By using the Kyoto University Critical Assembly (KUCA), a series of critical experiments was performed to measure the temperature coefficient of reactivity in a light-water-moderated and heavy-water-reflected cylindrical core loaded with highly-enriched-uranium (HEU) or medium-enriched-uranium (MEU) fuel. The measurement was performed for the approximately 20 to 70°C range to examine the effects of the size of light-water region in a heterogeneous multi-region type core, the reduced 235U enrichment, and the existence of boron burnable poison (BP) on this quantity by using six types of core configurations. In all the six types of cores, there were large light-water regions at the center of core and between the outer fuel region and the heavy-water reflector region, and it was found that these light-water regions caused a remarkably positive effect on the temperature coefficient of reactivity. In the present study, the temperature coefficients of the MEU core and the core without BP were more positive than those of the HEU core and the core with BP, respectively. The size of light-water region had a larger effect on the temperature coefficient rather than the reduced 235U enrichment and the existence of BP. The negative temperature coefficient would be realized by reducing the thickness of light-water layer existed in the core.
机译:通过使用京都大学临界组件(KUCA),进行了一系列临界实验,以测量负载有高浓铀(HEU)的轻水缓和重水反射圆柱型核的反应温度系数或中浓铀(MEU)燃料。在大约20至70°C的温度范围内进行测量,以检查异质多区域型岩心中轻水区域的大小,减少的235U富集以及是否存在硼可燃毒物(BP)的影响。通过使用六种类型的核心配置来获得此数量。在这六种类型的岩心中,在岩心的中心以及在外部燃料区域和重水反射器区域之间都有较大的轻水区域,发现这些轻水区域对核燃料产生了显着的积极影响。反应温度系数。在本研究中,MEU磁芯和不带BP的磁芯的温度系数分别比HEU磁芯和带BP的磁芯的温度系数正。轻水区的大小对温度系数的影响更大,而不是减少的235U富集和BP的存在。负温度系数可以通过减小芯中存在的轻水层的厚度来实现。

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