Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code

Zain, Jamal Al; Hajjaji, O. El; Bardouni, T. El; Boukhal, H.

doi:10.1016/j.jrras.2018.04.002

“…The predicted spectra exhibit a distribution pattern typical for thermal reactors, and consist of a thermal Maxwellian, followed by a flat epithermal neutron spectrum and a fission-like fast neutron component 46 . It is also similar to spectra reported for other thermal neutron beamlines, such as the Neutron Radiography Reactor (NRAD) at the Idaho National Laboratory (INL) in USA 47 , Thermal and Epi-thermal Neutron Irradiation Station (TENIS) at the Institut Laue-Langevin in France 48 , Syrian Miniature Neutron Source Reactor (MNSR) 49 , or Kalpakkam Mini reactor (KAIMINI) in India 50 . However, Giegel, et al 47 reported that the epithermal and fast neutron components are approximately 2 and 10 times higher than the thermal component.…”

Section: Discussionsupporting

confidence: 75%

A Monte Carlo model of the Dingo thermal neutron imaging beamline

Jakubowski

¹

,

Chacon

²

,

Tran

³

et al. 2023

Preprint

0

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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 spatial thermal neutron distribution obtained in-beam using gold foil activation and 10B4C-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 10B4C-coated microdosimeter measurements, respectively. The logarithms of the ratios of average simulated to experimental fluences in the thermal (Eth < 0.414 eV), epithermal (0.414 eV < Eepi < 11.7 keV) and fast (Efast > 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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“…The predicted spectra exhibit a distribution pattern typical for thermal reactors, and consist of a thermal Maxwellian, followed by a flat epithermal neutron spectrum and a fission-like fast neutron component 55 . It is also similar to spectra reported for other thermal neutron beamlines, such as the Neutron Radiography Reactor (NRAD) at the Idaho National Laboratory (INL) in USA 56 , Thermal and Epi-thermal Neutron Irradiation Station (TENIS) at the Institut Laue-Langevin in France 57 , Syrian Miniature Neutron Source Reactor (MNSR) 58 , or Kalpakkam Mini reactor (KAIMINI) in India 59 . Giegel et al 56 reported that the epithermal and fast neutron components are approximately 2 and 10 times higher than the thermal component.…”

Section: Discussionsupporting

confidence: 75%

A Monte Carlo model of the Dingo thermal neutron imaging beamline

Jakubowski,

Chacon,

Tran

et al. 2023

Sci Rep

1

0

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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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“…The spectrum energy of neutron can be classified into three regions, namely thermal (0<E<0.625 eV), intermediate (0.625 eV<E<0.5 MeV), and fast (E>0.5MeV). Fast neutrons are produced from fission reaction, whereas thermal and intermediate neutrons are results of neutron interaction with reactor materials, in form of slowing down process [9].…”

Section: Theory Neutron Sources In Reactormentioning

confidence: 99%

Estimation of Neutron and Prompt Photon Dose Rate Distribution in TMSR-500 Using McNp6

Pradana

¹

,

Utari

²

,

Suharyana

³

et al. 2022

Tri Dasa Mega

0

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Thorium Molten Salt Reactor-500 (TMSR-500), one of the Generation IV nuclear reactors, is designed by Thorcon International, Pte. Ltd, which is projected to be built in Indonesia. The reactor core is radially surrounded by B4C shielding, but not the upper part. As the silo hall sits above the reactor core and is accessible by reactor personnel, the dose rate must be calculated in the area to ensure the workers receive an annual dose below the acceptable limit. The dose rate from neutrons and photons as the result of fission reactions are the only sources to be calculated in this research, without taking the source from fission products into account. This research aims to obtain the dose rate distribution of neutrons and prompt photons using Monte Carlo code MCNP6. The reactor was assumed to operate at a nominal thermal power of 557 MWth. Dose rate calculation was obtained from flux Tally F4 and converted into dose rate using Dose Energy Dose Function (DEDF) factor. Conversion factors of flux to the dose were based on ICRP-21 and ANSI/ANS-6.1.1 1977. The result of the calculations showed that the distribution of neutron and prompt photon fluxes does not reach the silo hall.

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Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code

Cited by 8 publications

References 9 publications

A Monte Carlo model of the Dingo thermal neutron imaging beamline

A Monte Carlo model of the Dingo thermal neutron imaging beamline

A Monte Carlo model of the Dingo thermal neutron imaging beamline

Estimation of Neutron and Prompt Photon Dose Rate Distribution in TMSR-500 Using McNp6

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