Assessment of gamma-rays generated by the spontaneous fission source 252Cf using a Monte Carlo method

Khabaz, Rahim

doi:10.1016/j.anucene.2012.03.014

Cited by 20 publications

(8 citation statements)

References 12 publications

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“…This is to reduce the weight of the proposed device due to the radiological shielding requirements and the total neutron and photon dose rate for the operator. The measured and normalized neutron spectra of 252 Cf were taken from (Griffith et al, 1990), while the spectra of the gamma-ray photons associated with the 252 Cf source were taken from (Khabaz, 2012). To remove the gamma-ray photons associated with the 252 Cf source, it was located inside a sphere of Pb with 1 cm inner radius and 3 cm outer radius.…”

Section: Geometrymentioning

confidence: 99%

Monte Carlo modelling of a neutron-induced gamma-ray sensor for landmine or explosive detection

Elsheikh

2018

Journal of Radiation Research and Applied Sciences

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Monte Carlo simulations were carried out to model a thermal neutron-induced gamma-ray sensor for anti-personnel-landmine (APM) or explosive detection. This is done by employing the thermal neutron prompt gamma activation (TNPGA) technique. The neutron capture reaction on nitrogen 14 N(n,γ) 15 N is analyzed to detect the subsequent characteristic 10.8 MeV gamma rays. This is done by modelling a suitable geometry consisting of a point 252 Cf source placed inside a sphere of lead (Pb) which is contained in a cylinder of high density polyethylene (HDPE), together with a NaI (Tl) detector. The sensor geometry was optimized and the optimal configuration was selected to scan a plastic APM buried (2-10) cm. The Monte Carlo results obtained in terms of variations of the signal-to-background ratio, indicated the feasibility of employing 14 N(n,γ) 15 N neutron capture reaction for landmine detection and the suitability of the proposed sensor for airport explosives as well.

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Section: Geometrymentioning

confidence: 99%

Monte Carlo modelling of a neutron-induced gamma-ray sensor for landmine or explosive detection

Elsheikh

2018

Journal of Radiation Research and Applied Sciences

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“…Neutron detection is mainly based on gas counters, scintillators, or semiconductors. As mentioned in Ref [2], the A Gd ( 155 Gd and 157 Gd), 10 B, 7 Li are three kinds of elements having the highest neutron absorption cross section. Compared with 10B and 7 Li, the cross section for A Gd to capture neutron drops more rapidly with the increase of the neutron velocity, which makes it more suitable for thermal neutron detection.…”

Section: Introductionmentioning

confidence: 99%

“…Compared with 10B and 7 Li, the cross section for A Gd to capture neutron drops more rapidly with the increase of the neutron velocity, which makes it more suitable for thermal neutron detection. Recently the scintillators containing 6 Li or 10 B such as the LYSO crystal are proven to have a relatively high neutron detection efficiency and serve as good alternatives for 3 He gas proportional counters [3]. It can also achieve a great 𝑛/𝛾 discrimination through the pulse shape discrimination (PSD) method.…”

Section: Introductionmentioning

confidence: 99%

Study on the Possibility of Neutron Gamma Discrimination in GAGG Crystal

Zhang

Wang

et al. 2022

J. Phys.: Conf. Ser.

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The scintillators capable of neutron detection are being the research hotspot recently. In this manuscript, we investigated the possibility of cerium-doped gadolinium aluminium gallium garnet (GAGG: Ce) crystal to achieve neutron gamma discrimination through pulse shape discrimination (PSD) method. PSD is a method based on the principle that the waveforms of scintillation light differ for different particles. The experiments show that it’s hard for single GAGG crystal to distinguish the neutron from the gamma-ray. Therefore, a composite crystal made of gamma-sensitive crystal and GAGG crystal was furtherly developed. Using the 252Cf neutron source, the composite is proven to be capable of discriminating the neutrons from the gamma-ray and the corresponding FOM is 3.33.

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“…3 shows the gamma spectrum of a Cf source in dashed line, from data of ref. [33], and in continuous line the attenuated spectrum by using a 10 cm lead shield between the source and the detector. This shows how we avoid most of the gammas coming from the source to enter into the detector, leaving mainly fast neutrons emitted by the source.…”

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confidence: 99%

“…Figure3: Gamma spectrum emitted by a 252 Cf source taken from reference[33], in dashed line and the attenuated spectrum by the 10 cm lead shield in continuous line[34].…”

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confidence: 99%

Enhancing neutron detection capabilities of a water Cherenkov detector

Sidelnik

Asorey

Guarin

et al. 2020

Nuclear Instruments and Methods in Physics Research Section A:

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This is a PDF file of an article that has undergone enhancements after acceptance, such as the addition of a cover page and metadata, and formatting for readability, but it is not yet the definitive version of record. This version will undergo additional copyediting, typesetting and review before it is published in its final form, but we are providing this version to give early visibility of the article. Please note that, during the production process, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.

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Assessment of gamma-rays generated by the spontaneous fission source 252Cf using a Monte Carlo method

Cited by 20 publications

References 12 publications

Monte Carlo modelling of a neutron-induced gamma-ray sensor for landmine or explosive detection

Monte Carlo modelling of a neutron-induced gamma-ray sensor for landmine or explosive detection

Study on the Possibility of Neutron Gamma Discrimination in GAGG Crystal

Enhancing neutron detection capabilities of a water Cherenkov detector

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