氘-氘中子源束流转储的多目标优化

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-10 DOI:10.1016/j.anucene.2025.111859

Jingru Chen , Mingfei Yan , Zhanfei Liu , Xubin Zhang , Lucheng Yang , A.K. Jadi , Huasi Hu

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引用次数: 0

摘要

实验背景对中子实验数据质量有显著影响，特别是在密闭环境中，后壁的后向散射中子和伽马射线是主要来源。为了抑制这种现象，设计了一个由高密度聚乙烯（HDPE）、铅（Pb）、碳化硼（B4C）和钢组成的多层束流堆，用于氘-氘（DD）中子源设施的中子成像。采用非支配排序遗传算法（NSGA-II）和蒙特卡罗仿真代码MCNP6相结合的多目标优化方法。利用MCNP6计算了无束流、原始设计和优化设计三种构型下的后向散射中子和伽马射线的能谱和空间分布。优化后的束流与原设计相比，中子通量降低23%，伽马射线通量降低22%，总质量降低58%，验证了NSGA-II结合MCNP6的多目标优化方法是束流设计的有效工具。

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Multi-objective optimization of a beam dump for Deuterium-Deuterium neutron source

Experimental background significantly affects data quality in neutron experiments, with backscattered neutrons and gamma-rays from the back wall being the primary sources, especially in confined environments. To suppress this, a multilayer beam dump composed of high density polyethylene (HDPE), lead (Pb), boron carbide (B₄C), and steel was designed for the Deuterium-Deuterium (DD) neutron source facility for neutron imaging. A multi-objective optimization method combining the non-dominated sorting genetic algorithm (NSGA-II) and Monte Carlo simulation code MCNP6 was employed. The energy spectra and spatial distributions of backscattered neutrons and gamma-rays were obtained using MCNP6 for three configurations: without a beam dump, with the original design, and with the optimized design. Compared to the original design, the optimized beam dump reduced neutron flux by 23%, gamma-ray flux by 22%, and total mass by 58%, confirming that the multi-objective optimization method of NSGA-II combined with MCNP6 is an effective tool for beam dump design.

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来源期刊

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.