GEANT4 used for neutron beam design of a neutron imaging facility at TRIGA reactor in Morocco

Ouardi, A.; Machmach, A.; Alami, R.; Bensitel, A.; Hommada, A.

doi:10.1016/j.nima.2011.02.096

Cited by 5 publications

(4 citation statements)

References 8 publications

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“…Neutron radiography has been studied by many researchers and many different neutron radiography facilities have been developed [2][3][4]. According to current research and the structure of the BNCT reactor facility, the following sections will describe the simulation of the neutron collimator.…”

Section: Geant4 Simulation For the Thermal Neutron Collimatormentioning

confidence: 99%

“…According to Refs. [2][3][4][5] of the radiography collimator and the current situation of the thermal neutron exit of the BNCT reactor facility, a series of design requirements for the thermal radiography collimator are proposed. The requirements are as follows:…”

Section: Design Requirements For the Radiography Collimator And Simul...mentioning

confidence: 99%

“…Like X-ray radiography, the suitable radioactive source should be provided for neutron radiography. To obtain fast radiographic images and good position resolution of neutron radiography, the necessary neutron source used today should be provided by nuclear reactor or spallation neutron sources followed by a neutron collimator [2][3][4]. Furthermore, ideal neutron beams for neutron radiography should be parallel, monoenergetic and high flux, possessing no other radiation with good uniformity at its cross section.…”

Section: Introductionmentioning

confidence: 99%

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Neutron collimator design of neutron radiography based on the BNCT facility

Yang

俞伯祥

et al. 2014

Chinese Phys. C

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For the research of CCD neutron radiography, a neutron collimator was designed based on the exit of thermal neutron of the Boron Neutron Capture Therapy (BNCT) reactor. Based on the Geant4 simulations, the preliminary choice of the size of the collimator was determined. The materials were selected according to the literature data. Then, a collimator was constructed and tested on site. The results of experiment and simulation show that the thermal neutron flux at the end of the neutron collimator is greater than 1.0 × 10 6 n/cm 2 /s, the maximum collimation ratio (L/D) is 58, the Cd-ratio(Mn) is 160 and the diameter of collimator end is 10 cm. This neutron collimator is considered to be applicable for neutron radiography.

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Section: Geant4 Simulation For the Thermal Neutron Collimatormentioning

confidence: 99%

Section: Design Requirements For the Radiography Collimator And Simul...mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutron collimator design of neutron radiography based on the BNCT facility

Yang

俞伯祥

et al. 2014

Chinese Phys. C

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“…This is the first Monte Carlo model of the Dingo beamline and to our best knowledge, the first high-resolution CAD-based Monte Carlo model of a reactor-based thermal neutron beamline in general. However, similar models have been created in the past for other neutron beamlines, for instance the TRIUMF accelerator-based thermal neutron facility in Canada, modelled in MCPNX 10 ; the cold neutron facility (ICON) at the Swiss Spallation Neutron Source (SINQ), also modelled in MCPNX 11 , neutron imaging facility at TRIGA reactor in Morocco, modelled using Geant4 12 and the high energy neutron irradiation facility at the China Spallation Neutron Source, modelled in MCNPX 13 . These models were designed for a range of different purposes, such as the characterisation of the high-energy neutron field, coupling of the MCNPX and McStas packages, neutron beamline design or the generation of preliminary data for the physical experiments.…”

Section: Introductionmentioning

confidence: 99%

A Monte Carlo model of the Dingo thermal neutron imaging beamline

Jakubowski,

Chacon,

Tran

et al. 2023

Sci Rep

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In this study, we present a validated Geant4 Monte Carlo simulation model of the Dingo thermal neutron imaging beamline at the Australian Centre for Neutron Scattering. The model, constructed using CAD drawings of the entire beam transport path and shielding structures, is designed to precisely predict the in-beam neutron field at the position at the sample irradiation stage. The model’s performance was assessed by comparing simulation results to various experimental measurements, including planar thermal neutron distribution obtained in-beam using gold foil activation and $$^{10}$$ 10 B$$_{4}$$ 4 C-coated microdosimeters and the out-of-beam neutron spectra measured with Bonner spheres. The simulation results demonstrated that the predicted neutron fluence at the field’s centre is within 8.1% and 2.1% of the gold foil and $$^{10}$$ 10 B$$_{4}$$ 4 C-coated microdosimeter measurements, respectively. The logarithms of the ratios of average simulated to experimental fluences in the thermal (E$$_{th}<$$ th < 0.414 eV), epithermal (0.414 eV < E$$_{epi}<$$ epi < 11.7 keV) and fast (E$$_{fast}>$$ fast > 11.7 keV) spectral regions were approximately − 0.03 to + 0.1, − 0.2 to + 0.15, and − 0.4 to + 0.2, respectively. Furthermore, the predicted thermal, epithermal and fast neutron components in-beam at the sample stage position constituted approximately 18%, 64% and 18% of the total neutron fluence.

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