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首页> 外文期刊>Journal of nuclear science and technology >Fuel Temperature Coefficients of Reactivity for Heavy-Water-Moderated, Cluster-Type Fuel Lattices
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Fuel Temperature Coefficients of Reactivity for Heavy-Water-Moderated, Cluster-Type Fuel Lattices

机译:重水调节的簇状燃料格子的燃料温度反应性系数

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摘要

Temperature coefficients of reactivity have been measured up to 600°C on cluster-type UO2 fuel for three kinds of 235U enrichment and on a hollow cluster of sus-cladding tubes by using a hot He gas loop in a heavy-water-moderated, pressure-tube-type critical assembly. A new experimental method has been developed which accurately eliminates the reactivity disturbance caused by heat leakage in the measurement of an extremely small change in reactivity. The fuel (fuel pellet, cladding and pressure-tube) temperature coefficients of reactivity obtained for the temperature range below 300°C are +1.00±0.04, -3.48±0.13 and -6.36±0.25 in the unit of 10-5%Δk/k?°C for 0.2%, 0.7% and 1.5% 235U enrichment, respectively. In the higher temperature region above 300°C, each coefficient shifts to positive side by about 2×10-5%Δk/k?°C. Temperature coefficient of reactivity for the hollow cluster of sus-cladding tubes (cladding and pressure-tube) has a large constant value with positive sign, + (6.42±0.26) × 10-5%Δk/k?°C, all through the temperature range. A calculational model to analyze a hot-loop-type measurement of temperature coefficients with use of WIMS-D code was proposed and could be successfully applied to the present measurement.
机译:通过在重水调节的压力下使用热He气回路,在用于三种235U浓缩的团簇型UO2燃料和空心包层管的高达600°C的温度下,测量了反应温度系数管式关键组件。已经开发出一种新的实验方法,该方法可以在测量反应性极小的变化时准确消除由热泄漏引起的反应性干扰。在低于300°C的温度范围内获得的燃料(燃料芯块,覆层和压力管)反应性温度系数为+ 1.00±0.04,-3.48±0.13和-6.36±0.25,单位为10-5%Δk/分别以0.2%,0.7%和1.5%的235U浓缩至k?°C。在高于300℃的较高温度区域,每个系数向正侧偏移约2×10-5%Δk/ k?℃。整个包壳空心管(包壳和压力管)的反应温度系数具有较大的恒定值,带有正号+(6.42±0.26)×10-5%Δk/ k?°C。温度范围。提出了一种使用WIMS-D代码对温度系数的热循环式测量进行分析的计算模型,该模型可以成功地应用于当前的测量。

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