Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry

Sohrabpour, M.; Hassanzadeh, M.; Shahriari, M.; Sharifzadeh, Mohsen

doi:10.1016/s0969-8043(02)00130-6

Cited by 19 publications

(11 citation statements)

References 6 publications

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“…In addition, the frequently contain harmful substances, such as Pb. The MCNPX code is a representative program of the Monte Carlo method, and various studies on radiation shielding and protection have been carried out in Korea using this code [11][12][13][14][15]. Recently, MCNP6, which combines the functions of MCNP5 and MCNPX, was introduced.…”

Section: Introductionmentioning

confidence: 99%

Shielding Analysis of Metal Hydride-based Materials for Both Neutron and Gamma Rays Using Monte Carlo Simulation

Kwak¹,

Muth²,

Yang³

et al. 2021

Korean J. Met. Mater.

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Radiation causes damage to the human body, the environment, and electronic equipment. Shielding against neutron and gamma rays is particularly difficult because of their strong ability to penetrate materials. Conventional gamma ray shields are typically made of materials containing Pb. However, they pose problems in that Pb is a heavy metal, and human poisoning and/or pollution can result from the manufacturing, use, and disposal of these materials. In addition, neutron rays are shielded by materials rich in H2 or concrete. In the case of the latter, the manufacturing cost is high. Thus, it is necessary to develop a new multilayer structure that can shield against both neutron and gamma rays. We set up a simulation model of a multilayered structure consisting of metal hydrides and heavy metals, and then evaluated the simulations using Monte Carlo N-Particle Transport Code. Monte Carlo simulation is an accurate method for simulating the interaction between radiation and materials, and can be applied to the transport of radiation particles to predict values such as flux, energy spectrum, and energy deposition. The results of the study indicated the multilayer structure of ZrH2, U, and W could shield both neutron and gamma rays, thus showing potential as a new shielding material to replace Pb and concrete.

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Section: Introductionmentioning

confidence: 99%

Shielding Analysis of Metal Hydride-based Materials for Both Neutron and Gamma Rays Using Monte Carlo Simulation

Kwak¹,

Muth²,

Yang³

et al. 2021

Korean J. Met. Mater.

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“…To have the best performance using gamma sources with high activity, irradiating products in a broad range of densities, simplicity of product's transportation, and implementing the irradiation system in a short time which includes the arrangement of source pencils in the rack and the process of irradiating all the products, simulation of the multi-purpose gamma irradiator may be performed using the deterministic or probabilistic manners [4]. Sohrabpour and his colleagues have used the MCNP software [5] for dose rate mapping of a gamma irradiator; where, the results of the simulation were benchmarked against the experimental data obtained from three types of dosimeters (Fricke, ethanol chlorobenzene, potassium dichromate) [6]. A similar project was performed by Oliveira and his colleagues [3] in another irradiator gamma irradiator [7].…”

Section: Introductionmentioning

confidence: 99%

“…Then, both the routine GEANT4 code on a CPU processor and GPU-based GEANT4 algorithm on the GPU processor was used to model a gamma irradiator setup [14]. The results of the simulations were benchmarked against the published data [5]. Subsequently, with the aim of designing a new industrial irradiator system, the developed GPU-based GEANT4 code was used to determine its operational parameters.…”

Section: Introductionmentioning

confidence: 99%

Simulation of the multi-purpose gamma irradiator dose distribution based on the GEANT4 and GPU system

Razimanesh¹,

Hosseini²

2021

J. Inst.

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Gamma irradiation systems are used extensively in the industry in order to sterilize medical devices, disinfect hygienic products and increase the shelf life of agricultural products. The method of gamma irradiation is superior to the older methods of heat or chemical treatment because it is by far a simpler operation. In this method, only one parameter, the exposure time is controlled, whereas in the other mentioned methods five or six different parameters need to be controlled. The design of irradiation systems generally includes the size and the location of products, and the arrangement of source rack pencils. In order to optimize the design of the gamma irradiation systems, it is needed to study the product's dose distribution in a wide range of densities. The Monte Carlo algorithm is an effective way for simulating the irradiation systems which is being used by a variety of codes. Since this method requires a high computation time, it is necessary to speed up the simulation and design the systems by various methods such as using graphics processing units which having a highly parallel design makes them more suitable for algorithms that process a large number of data than central processing units. In this work, a GEANT4-based computational code is developed to adapt on the GPU using the CUDA programming. Since the developed GEANT4-based code utilizes a graphical processor of NVIDIA (in particular a series GTX660 Ti NVIDIA's GPU), it leads to speed up the process of simulation. Using this computational technique, a IR-136 gamma irradiator is simulated and the results of the simulation are benchmarked against previously published work. In the present work, a new setup of the industrial irradiator system is considered. The results of the simulations using CPU and GPU are compared with the available experimental dosimetry data. The dose calculation in the new setup is significantly faster using GPU in comparison to the GEANT4 code performed by CPU. The system *

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“…The manufacturer's calibration certificate states a dose rate of (4.43 ± 0.16) × 10 3 Gy/h on 08/28/1962 in the center of the exposure chamber. Figure 1 shows the isodoses provided by the manufacturer in 1962 [1].…”

Section: Introductionmentioning

confidence: 99%

“…The use of mathematical methods and radiation transport codes can reduce significantly this problem, although complex and time-consuming codes might be neces-sary [3,4]. Monte Carlo methods make possible to calculate various parameters like flux, fluence, energy spectra and absorbed dose [1,[5][6][7].…”

Section: Introductionmentioning

confidence: 99%

Retrieval of GammaCell 220 irradiator isodose curves with MCNP simulations and experimental measurements

Rodrigues¹,

Grynberg²,

Ferreira³

et al. 2010

Braz. J. Phys.

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Gamma irradiator facilities can be used in a wide range of applications such as biological and chemical researches, sterilization of medical devices and products. Dose mapping must be performed in these equipments in order to establish plant operational parameters, as dose uniformity, source utilization efficiency and maximum and minimum dose positions. The isodoses curves are measured using dosimeters or computer simulations. This work evaluates the absorbed dose in the CDTN/CNEN GammaCell Irradiation Facility, using the Monte Carlo N-Particles (MCNP) code.

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Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry

Cited by 19 publications

References 6 publications

Shielding Analysis of Metal Hydride-based Materials for Both Neutron and Gamma Rays Using Monte Carlo Simulation

Shielding Analysis of Metal Hydride-based Materials for Both Neutron and Gamma Rays Using Monte Carlo Simulation

Simulation of the multi-purpose gamma irradiator dose distribution based on the GEANT4 and GPU system

Retrieval of GammaCell 220 irradiator isodose curves with MCNP simulations and experimental measurements

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