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1.西安交通大学湖州中子科学实验室,浙江省湖州市313000
2.西安交通大学核科学与技术学院,陕西省西安市710049
3.华硼中子科技(杭州)有限公司,浙江省杭州市310000
Received:11 May 2025,
Revised:2025-07-14,
Accepted:20 July 2025,
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JIANG Quanxu, HAN Zheng, LIN Xingyang, et al. Optimization Design of Epithermal Neutron Field Based on D-D Neutron Source[J/OL]. Moren Journal, 2025.
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
6
cm
-2
·s
-1
,快中子污染降至5.5×10
-13
Gy·cm
2
,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奠定了基础。
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 using Monte Carlo simulation and a multi-objective optimization algorithm. First
the neutron source characteristics were determined by calculating the interaction of 200 keV deuteron ions with a deuterated titanium target using the Geant4 code. Second
with the objectives of maximizing the epithermal neutron flux and minimizing the fast neutron contamination and thermal neutron fraction
the BSA based on the D-D neutron source was optimized using the MCNP6 code combined with a genetic algorithm. Finally
the beam distribution characteristics were evaluated using a three-dimensional water phantom. The results show that the optimized epithermal neutron flux reaches 2.65×10
6
cm
-2
·s
-1
the fast neutron contamination is reduced to 5.5×10
-13
Gy·cm
2
and the thermal neutron fraction is 0.0134
all of which are better than the expected indicators. The neutron field at the exit of the BSA exhibits good symmetry and directionality in spatial distribution. Th
is study provides reliable experimental conditions for the development and calibration of detectors and lays the foundation for the miniaturization design of BNCT devices.
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