首页> 外文会议>ANS Nuclear Criticality Safety Division topical meeting >EVALUATION OF SCALE 6.1.2 TSUNAMI MODULE FOR SELECTION OF REPRESENTATIVE BENCHMARKS FOR VALIDATION OF CRITICALITY SAFETY STUDIES
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EVALUATION OF SCALE 6.1.2 TSUNAMI MODULE FOR SELECTION OF REPRESENTATIVE BENCHMARKS FOR VALIDATION OF CRITICALITY SAFETY STUDIES

机译:6.1.2海啸模块评估代表性安全性评估的有效性评估

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The validation process of the codes used in criticality safety studies is an indispensable step in determining the permissible criteria for the criticality safety calculations. Several methods exist to choose critical experiments representative of the configuration of calculation leading to the maximum of reactivity, including one, the so-called "expert" approach, based on macroscopic physical parameters (physicochemical material, average energy of neutron leading to a fission, ...). Although this approach is most commonly used by criticality experts in France, it has the disadvantage of having to know, in the most exhaustive way possible, all the criticality experiments available to select the experiments representative of the case of computation studied. Consequently, the search for tools enabling a pre-selection of the critical experiments that are closest neutronically to the situation studied would make it possible to reduce this step in the development of a criticality safety study. The objective of the paper is to present, on a set of configurations resulting from criticality calculation notes where validation process has already been done using expert approach, a comparison of the results of correlation coefficient produced by SCALE 6.1.2 TSUNAMI module in regards to benchmarks selected by "expert" approach.
机译:关键安全性研究中使用的代码的验证过程是确定关键性安全性计算的允许标准中必不可少的步骤。有几种方法可以选择能代表最大反应性的计算配置的临界实验,包括一种基于宏观物理参数(理化材料,导致裂变的中子平均能量, ...)。尽管此方法是法国的关键性专家最常用的方法,但它的缺点是必须以最详尽的方式了解所有可用的关键性实验,以选择代表所研究计算案例的实验。因此,寻找能够预先选择最接近于所研究情况的关键实验的工具,将有可能在关键安全性研究的开发中减少这一步骤。本文的目的是,在已经由专家方法完成验证过程的,由临界计算记录得出的一组配置中,对SCALE 6.1.2 TSUNAMI模块相对于基准所产生的相关系数的结果进行了比较。通过“专家”方法选择。

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