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作 者:刘晓波[1,2] John D.Bess Margaret A.Marshall
机构地区:[1]中广核久源(成都)科技有限公司,四川成都610093 [2]中国工程物理研究院核物理与化学研究所,四川绵阳621900 [3]Idaho National Laboratory, Idaho Falls 83415
出 处:《原子能科学技术》2017年第5期803-810,共8页Atomic Energy Science and Technology
基 金:国家留学基金委国家公派高级研究学者及访问学者(含博士后)项目资助([2013]3018)
摘 要: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 experiments data of critical assemblies and formatting the benchmark data set in the requirements of International Criticality Safety Benchmark Evaluation will enrich the International Handbook of Evaluated Criticality Safety Bench- mark Experiments, and can be used in the nuclear field for nuclear data verification, numerical software validation, reactor design and criticality analysis, et al. Firstly, the methodology with its foundation for the uncertainty analysis of experimental ke; was described, and the requirements with its approaches for modeling critical assembly were introduced, then three configurations of critical assemblies (different diameter HEU metal annuli with internally reflected graphite cylinder) with their experimental keff results were introduced, lastly the uncertainties of experimental keff and the biases of modeling the experimental of experimental keff with th ments for the inclusion of configurations were performed eir uncertainties were achieved. and the benchmarking results The results meet the requirethe International Handbook of Evaluated Criticality Safety Benchmark Experiments.
关 键 词:金属高浓铀 石墨 临界安全 不确定度分析 模型化处理 基准分析
分 类 号:TL411[核科学技术—核技术及应用]
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