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将临界装置实验数据进行基准化分析并形成满足国际临界安全分析评价标准的基准实验数据,可充实临界安全实验基准数据库,进而可应用于核数据检验、数值模拟程序验证、反应堆设计和临界安全分析等领域。本文阐述了临界装置实验keff的不确定度分析原理及处理方法、装置模型化要求及处理方法。然后采用该方法根据3个高浓铀圆环(内含石墨圆柱)临界装置的基本条件和实验结果,完成了实验keff的不确定度分析和装置模型化处理时的偏倚分析,得到了这3个临界装置在模型化处理后的keff值及不确定度。研究结果满足国际临界安全基准数据库收录的要求。
Benchmarking the critical experimental data and forming baseline experimental data meeting the international criticality safety analysis and evaluation criteria can enrich the critical safety experimental data base which can be applied to nuclear data validation, numerical simulation verification, reactor design and critical safety analysis Other fields. This article describes the critical device experiment keff uncertainty analysis principle and processing methods, device modeling requirements and processing methods. Then, based on the basic conditions and experimental results of the critical devices for three highly enriched uranium rings (including graphite cylinders), the uncertainty analysis of the experimental keff and the analysis of the bias when the device is modeled are completed. The critical value of the critical device after modeling and the uncertainty. The results meet the requirements of the International Criticality Safety Database.