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首页> 外文期刊>Journal of nuclear science and technology >Analysis of Core Physics Experiments on Fresh and Irradiated PWR UO)_2 Fuels in the REBUS Program
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Analysis of Core Physics Experiments on Fresh and Irradiated PWR UO)_2 Fuels in the REBUS Program

机译：REBUS计划中的新鲜和辐射PWR UO）_2燃料的核心物理实验分析

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摘要

Critical experiments of two cores each loaded with fresh 5×5 test PWR-type fuel rods of~(235)U enrichment of 3.8 wt% or irradiated 5×5 test rods of rod average burnup of 55 GWd/t in the REBUS program were analyzed using diffusion, transport, and continuous-energy Monte Carlo calculation codes coupled with nuclear data libraries based on JENDL-3.2 and JENDL-3.3. Biases in effective multiplication factors k_eff's of the critical cores were about -1.2%△k for the diffusion calculations (JENDL-3.2), -0.5%△k for the transport calculations (JENDL-3.3), and -0.5 and 0.1%△k for the Monte Carlo calculations (JENDL-3.3 and JENDL-3.2, respectively). The measured core fission rate and Sc- or Co-activation rate distributions were generally well reproduced using the three types of calculation. The burnup reactivity determined using the measured water level reactivity coefficients was-2.35 ± 0.07△k/kk'. The calculated result of the Monte Carlo calculations agreed with it; however, the diffusion and transport calculations overestimated the absolute value by about 7%, which would be mainly attributed to the errors in the calculation of the reactivity caused by changing the fuel compositions from fresh fuel to irradiated fuel.
机译：在REBUS程序中，对两个分别装有新鲜的5×5测试PWR型燃料棒（〜（235）U浓缩度为3.8 wt％）或辐照的5×5测试棒的棒芯平均燃耗为55 GWd / t的两个芯进行了关键实验。使用扩散，传输和连续能量蒙特卡洛计算代码以及基于JENDL-3.2和JENDL-3.3的核数据库进行分析。关键核的有效倍增系数k_eff的偏差对于扩散计算（JENDL-3.2）约为-1.2％△k，对于迁移计算（JENDL-3.3）约为-0.5％△k，以及-0.5和0.1％△k用于蒙特卡洛计算（分别为JENDL-3.3和JENDL-3.2）。使用三种类型的计算方法通常可以很好地再现所测得的核裂变率和Sc-或Co-活化率分布。使用测得的水位反应性系数确定的燃耗反应性为-2.35±0.07△k / kk'。蒙特卡洛计算的计算结果与之相符；然而，扩散和迁移计算将绝对值高估了约7％，这主要归因于由于将燃料成分从新鲜燃料改为辐照燃料而导致的反应性计算中的误差。

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