核反应堆中子输运的随机理论

IF 0.7 4区工程技术 Q3 MATHEMATICS, APPLIED Journal of Computational and Theoretical Transport Pub Date : 2021-07-29 DOI:10.1080/23324309.2021.1942062

R. Y. Nesterenko

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引用次数: 0

摘要

摘要这项工作是ICTT-26会议上提交的报告的扩展版本。在第一部分中，我们推导了核反应堆分布模型中整数中子和延迟中子前兆概率密度的前向和后向时间依赖线性随机方程。在第二部分中，我们推导了反应堆在接近临界状态下的分布临界随机方程，并得到了渐近中子数概率密度函数的解析解。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Stochastic Theory of Neutron Transport in Nuclear Reactor

Abstract The work is an extended version of the report presented at the conference ICTT-26. In the Part I we derive the forward and backward time-dependent linear stochastic equations for probability density of the integer number of neutrons and delayed neutron precursors in distributed model of a nuclear reactor. In the Part II we derive the distributed criticality stochastic equations and obtain the analytical solutions for asymptotic neutron number probability density function for a reactor in a close-to-critical state.

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来源期刊

Journal of Computational and Theoretical Transport Mathematics-Mathematical Physics

CiteScore

1.30

自引率

0.00%

发文量

期刊介绍： Emphasizing computational methods and theoretical studies, this unique journal invites articles on neutral-particle transport, kinetic theory, radiative transfer, charged-particle transport, and macroscopic transport phenomena. In addition, the journal encourages articles on uncertainty quantification related to these fields. Offering a range of information and research methodologies unavailable elsewhere, Journal of Computational and Theoretical Transport brings together closely related mathematical concepts and techniques to encourage a productive, interdisciplinary exchange of ideas.