氘氘中子源超热中子场优化设计

姜泉旭; 韩正; 林兴洋; 杨尚晖; 代雨奇; 张天骄; 陈田; 马宝龙; 王盛

doi:10.7652/xjtuxb202512009

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氘氘中子源超热中子场优化设计

专题中子源优化 | 更新时间：2025-12-08

- 氘氘中子源超热中子场优化设计
- Optimized Epithermal Neutron Field Design Based on D-D Neutron Source
- 西安交通大学学报 2025年59卷第12期页码：105-116
- 作者机构：
- 作者简介：
  
  作者简介：姜泉旭（1997—），男，博士生；
  马宝龙（通信作者），女，助理教授。
- 基金信息：
  
  国家自然科学基金资助项目(12375159;12105214);国家重点研发计划资助项目。(2023YFA1008600)
- DOI：10.7652/xjtuxb202512009
  中图分类号： TL99
- 收稿：2025-05-11，
  
  纸质出版：2025-12-10
- 稿件说明：
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姜泉旭, 韩正, 林兴洋, 等. 氘氘中子源超热中子场优化设计[J]. 西安交通大学学报, 2025,59(12):105-116.

JIANG Quanxu, HAN Zheng, LIN Xingyang, et al. Optimized Epithermal Neutron Field Design Based on D-D Neutron Source[J]. Journal of Xi'an Jiaotong University, 2025, 59(12): 105-116.
姜泉旭, 韩正, 林兴洋, 等. 氘氘中子源超热中子场优化设计[J]. 西安交通大学学报, 2025,59(12):105-116. DOI： 10.7652/xjtuxb202512009.

JIANG Quanxu, HAN Zheng, LIN Xingyang, et al. Optimized Epithermal Neutron Field Design Based on D-D Neutron Source[J]. Journal of Xi'an Jiaotong University, 2025, 59(12): 105-116. DOI： 10.7652/xjtuxb202512009.

摘要

为获得适用于硼中子俘获治疗中子探测器性能验证的超热中子场，利用蒙特卡罗模拟和多目标优化算法，设计了基于氘氘中子源的束流整形体。首先，通过Geant4程序计算，确定了能量为200 keV氘离子轰击氘钛靶的中子源项特性；其次，以超热中子通量最大化、快中子污染和热中子占比最小化为优化目标，结合MCNP6程序和遗传算法对基于氘氘中子源的束流整形体进行多目标优化；最后，采用三维水箱评价了束流的分布特性。研究结果表明：优化后的超热中子通量达2.65×10

/（cm

·s），快中子污染降至5.5×10

-13

Gy·cm

，热中子占比为0.0134，均优于预期指标；束流整形体出口的中子场在空间分布上具有良好的对称性和指向性。该研究为探测器研制与标定提供了可靠的实验条件，同时也为硼中子俘获治疗装置的小型化设计提供了思路。

Abstract

To obtain an epithermal neutron field suitable for the performance validation of neutron detectors used in boron neutron capture therapy（BNCT）

a beam shaping assembly（BSA）based on a deuterium-deuterium（D-D）neutron source was designed based on Monte Carlo simulation and a multi-objective optimization algorithm.First

the Geant4 code was used to calculate the interaction of 200 keV deuteron ions with a deuterated titanium target for determining the characteristics of the neutron source.Second

multi-objective optimization of the D-D neutron source-based BSA was conducted by using the MCNP6 code combined with a genetic algorithm to maximize the epithermal neutron flux and minimize the fast neutron contamination and thermal neutron fraction. Finally

a three-dimensional water phantom was employed to evaluate distribution characteristics of the beam.The results show that the epithermal neutron flux after optimization reached 2.65×10

/（cm

·s）

the fast neutron contamination was reduced to 5.5×10

-13

Gy·cm

and the thermal neutron fraction was 0.0134

all better than the expected values.The neutron field at the exit of the BSA exhibited good symmetry and directionality in spatial distribution.This study is intended to provide reliable experimental conditions for the development and calibration of detectors

providing an idea for the miniaturization design of BNCT devices.

关键词

Keywords

references

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