SORA原型装置临界实验的基准化分析

Benchmarking Critical Experiment of SORA Mockup

  • 摘要: 临界装置实验数据的基准化分析是充实临界安全实验基准数据手册的必要条件。本文首先介绍了SORA(Sorgente Rapida Reactor)原型装置的活性区结构组成、临界实验等情况,然后对15个典型的临界实验数据进行了不确定度分析,其实验keff不确定度在0.002 3~0.002 7范围内,并进一步分析了对实验装置进行模型化处理的偏倚及其不确定度,最后得到了SORA原型装置基准模型的keff值及其不确定度。SORA模型的数值计算结果与实验基准化分析的keff值相比略低,其最大相对偏差小于1%。研究结果满足临界安全实验基准数据手册收录的要求。

     

    Abstract: Benchmarking the critical experiments of nuclear assembly is a prerequisite for enriching the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Firstly, the core configurations and critical experiments of the SORA (Sorgente Rapida Reactor) mockup were introduced. Then the uncertainties of experimental keff for fifteen typical critical experiments were evaluated, resulting in the range of 0.002 3-0.002 7, and the biases with their uncertainties for modelization of the experiments were analyzed. Lastly the benchmarking results of keff with uncertainties were achieved. The results of numerical calculation of the SORA model are a little less than the benchmarking results of experiments in which the most relative deviation is less than 1%. The results meet the requirements for the inclusion of the International Handbook of Evaluated Criticality Safety Benchmark Experiments.

     

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