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本文介绍了高浓铀(90%~(235)U)石墨慢化体系的临界性研究情况,包括核子比从2605至12734之间的一系列临界实验结果、误差分析,以及一维、二维的几种数值计算程序的计算结果。并且对理论模型和计算方法与实验值间的偏差进行了综合分析。结果表明正确的运用这套计算方法可以满足这种类型反应堆的临界性设计要求。
This paper presents the critical studies on the moderator system of highly enriched uranium (90% ~ (235) U) graphite, including a series of critical experimental results with error of 2605 to 12734 and error analysis, as well as one-dimensional and two- Several numerical calculation of the calculation results. And the theoretical model and calculation methods and experimental values of the deviation between a comprehensive analysis. The results show that the correct use of this calculation method can meet the critical design requirements of this type of reactor.