Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

Koreshi, Zafar Ullah; Khan, Hassan

doi:10.1115/1.4032702

Cited by 6 publications

(5 citation statements)

References 8 publications

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“…The algorithm introduces the concepts of selection, crossover and variation in biological evolution, and determines the priority of reproduction of an individual by comparing the individual's adaptability to the environment, so as to achieve the purpose of screening the optimal results. In recent years, genetic algorithms have also been applied in the field of nuclear technology and design, such as shielding material optimization, moderator optimization, radiation imaging and other fields [29][30][31][32]. Due to its population-based nature, genetic algorithms are well suited for solving multi-objective optimization problems.…”

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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“…For simulation of coupled neutron-gamma transport, the Monte Carlo code MCNP (Maučec & De Meijer, 2002;Team, 2003;Baysoy & Subaşı, 2013) has been extensively used and is regarded as a reliable tool for the design of nuclear systems (Uchai et al, 2008). This paper, based on the knowledge of design sensitivity leading to optimisation of EDS components (Koreshi & Khan, 2016Khan et al, 2017) considers a portable EDS incorporating a neutron source and detection systems, which fits into a common briefcase of dimension 40 cm × 30 cm × 8 cm. The detection efficiency and radiation dose are computed using the Monte Carlo code MCNP5 to present a useful and efficient portable design.…”

Section: Sourcementioning

confidence: 99%

Characteristic photon yields from thermal neutron activation of explosives for a portable detection system

Khan

Koreshi²,

Sheikh³

et al. 2021

J. Natn. Sci. Foundation Sri Lanka

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Explosive detection systems (EDS) based on thermal neutron activation can be used for detection and identification of concealed explosives such as trinitrotoluene, cyclonite, and ammonium nitrate (NH 4 NO 3 ). Activation results in emission of characteristic gamma rays of constituents whose relative intensities yield atomic fractions of the explosives and instant identification. Applications of EDS can also be at airports and seaports as well as in vehicles. Such systems have been studied, developed and tested and are being refined in their design and functionality as several issues still need to be resolved, such as the associated high radiation dose and development of fast algorithms for their identification. This paper considers a portable EDS, incorporating a neutron source and radiation detection systems, which can fit into a portable briefcase of dimensions 40 cm × 30 cm × 8 cm. The detection efficiency and radiation dose are computed by carrying out simulations, to estimate the strengths of characteristic photon yields, using the Monte Carlo code MCNP5 to present a useful and efficient engineering design. Two factors of concern were found to be the excessive photons from material of least interest ( 10 B, Ca, Pb) and the excessive radiation dose in the immediate vicinity of a portable system. However, an accurate estimate of the H/N ratio was obtained with simulation carried out for ~1kg concealed TNT explosive. The ratio was found to be ~1.61 which is very close to the actual ratio (1.67). Thus, the accurate identification of TNT explosives can be efficiently carried out by such a portable system.

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“…The method has been used in dealing with modeling and optimization problems [13], optimizing beam components in accelerators [14]. Other achievements in the application of GA are the determination of optimum thickness in moderator design [15] and gamma shielding design to determine the best composition of some materials [16]. The latest achievement is the use of Multi-Objective Genetic Algorithm (MOGA) and Monte Carlo optimization method in optimizing the beam port of ITU reactor to produce epithermal neutron beams for BNCT purposes [11].…”

Section: Introductionmentioning

confidence: 99%

Optimization of double layered beam shaping assembly using genetic algorithm

Bilalodin

Kusminarto

Suparta

et al. 2018

Polish Journal of Medical Physics and Engineering

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The genetic algorithm method is a new method used to obtain radiation beams that meet the IAEA requirements. This method is used in optimization of configurations and compositions of materials that compose double layered Beam Shaping Assembly (BSA). The double layered BSA is modeled as having two layers of material for each of the components, which are the moderator, reflector, collimator, and filter. Up to 21st generation, the optimization results in four (4) individuals having the capacity to generate the most optimum radiation beams. The best configuration, producing the most optimum radiation beams, is attained by using combinations of materials, that is by combining Al with either one of CaF2 and PbF2for moderator; combining Pb material with either Ni or Pb for reflector; combining Ni and either FeC or C for collimator, and FeC+LiF and Cd for fast and thermal neutron filter. The parameters of radiation resulted from the four configurations of double layer BSA adequately satisfy the standard of the IAEA.

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Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

Cited by 6 publications

References 8 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

Characteristic photon yields from thermal neutron activation of explosives for a portable detection system

Optimization of double layered beam shaping assembly using genetic algorithm

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