利用前向传输理论计算核保障措施中的多重性时刻

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-23 DOI:10.1016/j.anucene.2024.111046
Liliane Basso Barichello , Imre Pázsit
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引用次数: 0

摘要

核保障措施的倍率计数的理论基础在于计算物品发射的中子数的阶乘矩。计算这些阶乘矩的传统方法采用所谓的点模型,其中忽略了中子在物品中的空间传输,而最近的理论框架则是通过单速传输模型重新推导出来的,该模型本质上属于后向(邻接)类型。所产生的矩积分方程通过碰撞数型(迭代核或诺依曼数列)展开进行数值求解。在本文中,我们展示了最初为直接(正向)传输问题开发的有效分析方法,可以与邻接型矩方程的求解联系起来。本文对理论进行了描述,并给出了部分代表性案例的定量结果。对该方法的精度和计算速度进行了研究,并与碰撞数扩展法进行了比较。定量结果还使我们对流出中子的乘法过程的统计特性有了一些新的认识。
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Calculation of the multiplicity moments in nuclear safeguards with forward transport theory
The theoretical basis of multiplicity counting of nuclear safeguards lies in the calculation of the factorial moments of the number of neutrons emitted from the item. While the traditional method to derive these moments uses the so-called point model in which the spatial transport of neutrons in the item is neglected, the theoretical framework has recently been re-derived in a one-speed transport model, which is inherently of the backward (adjoint) type. The arising integral equations for the moments were solved numerically with a collision number type (iterated kernel or Neumann-series) expansion. In this paper, we show that effective methods of analytical character, originally developed for direct (forward-type) transport problems, can be associated with the solution of the adjoint-type moment equations. The theory is described, and quantitative results are given for selected representative cases. The accuracy and computational speed of the method is investigated and compared favourably with those of the collision number expansion method. The quantitative results also lend some new insight into the properties of statistics of the multiplicative process for the exiting neutrons.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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