arXivDaily arXiv每日学术速递 周一至周五更新
arXiv 1410.2148nucl-th
收藏

两种中子多重数分布计算方法的比较

A comparison between two evaluations of neutron multiplicity distributions

J. P. Lestone

摘要:

在MCNP 6中,用户可以根据Lestone进行的评估(LA-UR-05-0288),使用自发裂变和中子诱发裂变的多重性分布。该评估假设多重性分布为高斯分布,并调整标准差以重现测量的二阶和三阶阶乘矩。在MCNPX中,用户可以选择使用Santi和Miller(LA-UR-07-6229)对可用实验数据进行评估后,使用自发裂变的多重性分布。本文比较了这两种方法计算的自发裂变多重数分布和相应的阶乘矩。除了238钚的自发裂变外,所有的差异都很小或在实验误差范围内。钚-238的评估是基于1956年获得的数据。我们建议重新测量238 Pu多重数分布。考虑到两种评价之间的良好一致性,评价的选择对自发裂变的建模几乎没有影响。然而,我们建议采用LA-UR-05-0288中的评估作为MCNP默认值,因为它还包括中子诱发裂变的推荐分布。

英文摘要:

Within MCNP6, users can use multiplicity distributions for spontaneous and neutron-induced fission from an evaluation performed by Lestone (LA-UR-05-0288). This evaluation assumes the multiplicity distributions are Gaussian and adjusts the standard deviations to reproduce measured 2nd and 3rd factorial moments. In MCNPX, users have the option of using multiplicity distributions for spontaneous fission using an evaluation of the available experimental data by Santi and Miller (LA-UR-07-6229). The spontaneous fission multiplicity distributions and corresponding factorial moments from these two evaluations are compared in the present paper. The differences are minor or within experimental errors for all but the spontaneous fission of 238Pu. The 238Pu evaluations are based on data obtained in 1956. We recommend that the 238Pu multiplicity distribution be re-measured. Given the good agreement between the two evaluations, the choice of evaluation will make little difference for the modeling of spontaneous fission. However, we suggest that the evaluation in LA-UR-05-0288 be adopted as the MCNP default because it also includes recommended distributions for neutron induced fission.

机构、总结、中文摘要均由AI分析而来,可能存在错误,请以论文正文为准。

↑