An iterative prediction method for designing the moderator used for the boron neutron capture therapy

Zhang, Ruiqin; Yu, Yangyi; Zhang, Zhi; Yang, Yigang

doi:10.1002/mp.15339

Cited by 4 publications

(2 citation statements)

References 24 publications

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“…Genetic algorithms are increasingly used in material optimization in the field of nuclear engineering, and they show better optimization results than traditional experience [25]. Recently, Yang's team proposed an iterative prediction method in which the neutron transportation properties of one material were characterized by a reflection matrix and a transmission matrix [33]. The matrixes of different materials were calculated by the Monte Carlo method.…”

Section: Two Methods Of Realizing Multi-objective Optimizationmentioning

confidence: 99%

Optimization of moderator materials by NSGA II based on macroscopic cross-sections: applications in accelerator neutron sources

Zhong

Yuan

et al. 2023

J. Inst.

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In recent years, genetic algorithms have been applied in nuclear technology design, which have been shown to produce optimized results more efficiently than traditional enumeration methods. This advancement in optimization techniques is particularly useful in the field of nuclear technology design, where complexity is high and decision-making time is critical. It can be used to optimize moderator materials for ANS to find composite materials that provide high neutron beam quality. At present, the direct combination of Monte Carlo method and genetic algorithm requires a lot of computing resources and time. And the weights of different optimization objectives are controversial. Thus, we propose a two-step method based on NSGA II, which uses macroscopic section as the intermediate parameters for optimization. It can greatly reduce the time of genetic algorithm optimization. The method is applied to the PAFA project of Sun Yat-sen University, the computational speed has been increased by 50 times based on a 50-generation optimization. And the results of the genetic algorithm show that the neutron beam obtained by using composite materials as moderator is 30.8% better than that obtained by using only MgF2 as moderator. The two-step genetic algorithm optimization has shown its great potential in the optimization problem of moderator materials.

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Section: Two Methods Of Realizing Multi-objective Optimizationmentioning

confidence: 99%

Optimization of moderator materials by NSGA II based on macroscopic cross-sections: applications in accelerator neutron sources

Zhong

Yuan

et al. 2023

J. Inst.

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“…Due to the low probabilities accompanying the neutrons’ moderation and detection process, however, the practical applications of neutron inherently demand that neutron sources should deliver intense neutron beams to meet the requirements of counting statistics. For example, a BNCT system requires a higher than 10 14 n/s neutron yield of the neutron source to generate epithermal neutrons with flux higher than 10 9 cm −2 s −1 for an effective treatment [ 5 ]. A thermal neutron imaging system, with a typical aspect ratio of 100:1, demands a neutron yield of 10 14 n/s, when the efficiency of moderating fast neutrons to thermal neutrons is 10% and the required thermal neutron flux at the position of the detector is about 10 6 n/cm 2 /s, in order to complete a neutron imaging within an acceptable temporal duration (for example, several minutes).…”

Section: Introductionmentioning

confidence: 99%

A Design for the High Yield Photoneutron Source Target Station

Lai

Yang

2022

Materials

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Low energy accelerator driven neutron sources are promising candidates to obtain a neutron yield as high as 1014 n/s, which is required for a variety of applications, such as boron neutron capture therapy, neutron imaging, and neutron scattering. The methods to generate neutrons can be divided into two categories: hadron-based and photon-based methods. In order to better understand which kind of source would be the better choice for delivering a brilliant neutron beam robustly, in this paper, the underlying principles of neutron production, as well as the simulation results of neutron yield, target heat dissipation, thermal stress, and reaction byproducts concentration of these two types of neutron sources, will be elaborated on. A preliminary photoneutron target station design based on a 50 MeV/50 kW electron linear accelerator, including the optimized neutron yield, thermal hydraulic analysis, and shielding calculation, is presented as well to demonstrate the method to deliver brilliant thermal neutron beam of 1.03 × 1010 cm−2 s−1 sr−1.

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Efficient optimization of an accelerator neutron source for neutron capture therapy using genetic algorithms

Ge,

Zhong,

Murata

et al. 2024

Medical Physics

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BackgroundIn recent years, genetic algorithms have been applied in the field of nuclear technology design, producing superior optimization results compared to traditional methods. They can be employed in the design and optimization of beam shaping assemblies (BSA) BSA to obtain the desired neutron beams. But it should be noted that the direct combination of Monte Carlo methods with genetic algorithms requires a significant amount of computational resources and time.PurposeDesign and optimize BSA more efficiently to achieve neutron beams that meet specified recommendations.MethodsWe propose an approach of NSGA II with crucial variables which are identified by multivariate statistical techniques. This approach significantly reduces the problem sizes, thus reducing the time required for optimization. We illustrate this methodology using the example of BSA design for AB‐BNCT.ResultsThe computational efficiency has tripled with crucial variables. By using NSGA II, we obtained optimized models conforming to both the new and old version IAEA BNCT guidelines through a single optimization process and subjected them to phantom analysis. The results demonstrate that models obtained through this method can meet the IAEA recommendations with deep advantage depth (AD) and high absorbed ratio (AR).ConclusionThe genetic algorithm with crucial variables displays tremendous potential in addressing BSA optimization challenges.

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An iterative prediction method for designing the moderator used for the boron neutron capture therapy

Cited by 4 publications

References 24 publications

Optimization of moderator materials by NSGA II based on macroscopic cross-sections: applications in accelerator neutron sources

Optimization of moderator materials by NSGA II based on macroscopic cross-sections: applications in accelerator neutron sources

A Design for the High Yield Photoneutron Source Target Station

Efficient optimization of an accelerator neutron source for neutron capture therapy using genetic algorithms

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