Monte Carlo simulation study on TeO2–Bi2O–PbO–MgO–B2O3 glass for neutron-gamma 252Cf source

Malidarre, Roya Boodaghi; Akkurt, I.

doi:10.1007/s10854-021-05776-y

Cited by 68 publications

(16 citation statements)

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“…To nd the Skin dose contamination of the 252 Cf source using SDCC for wide energy regions. In radiation, works have been studied especially in terms of shielding and other purposes besides contamination in literature [16][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31][32][33]. Using ICRP107, the 252 Cf radionuclide source is extracted and the results are provided in Table 3.…”

Section: Resultsmentioning

confidence: 99%

“…Introduction 252 Cf radionuclide with a half-life of 2.645 years is a popular source in medicine, industry, targeted radionuclide therapy, … [1][2][3]. One microgram of 252 Cf source emits 2.314 × 10 6 neutrons.s -1 and 1.322 × 10 7 photons.s -1 [2][3][4][5][6]. The isotope 252 Cf decays through alpha emission (~ 97%) into 248 Cm and by spontaneous ssion (~ 3%) into different ssion products which results in both neutrons and gamma photons.…”

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confidence: 99%

“…The isotope 252 Cf decays through alpha emission (~ 97%) into 248 Cm and by spontaneous ssion (~ 3%) into different ssion products which results in both neutrons and gamma photons. A large amount of detected gamma photons of 252 Cf emission have a continuous spectrum with a wide range of energy from 0 to 10 MeV [3][4]. Handling of 252 Cf radionuclide source can lead to contamination of the skin surface in case of an accident.…”

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A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Malidarre¹,

Akkurt²

2023

Preprint

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Handling of 252Cf radionuclide source can lead to contamination of the skin surface in case of an accident. There is still an increasing demand to have dose conversion coefficients of each primary particle and different sources. On the other hand, there is no literature that presents actual values and methods for determining skin dose contamination and its coefficients for 252Cf source. Thus, this paper is concerned with quantifying the received dose rate and its coefficients in the skin as a result of a contamination scenario. The equivalent and absorbed dose rates, as well as SDCC, are estimated using MCNPX Monte-Carlo simulation’s well-established calculation code in the skin. Two methods i.e. watt fission and doppler effect are proposed for calculating particles’ spectra, and consequently, with the help of flux–to–dose conversion function Equivalent dose rates are derived. Also, the SDCC on the skin surface for different particles is obtained and these values are reported for 252Cf radionuclide. The particles of interest in this study are neutrons and gamma photons. The new dose coefficients allow the estimation of the skin dose contamination in radionuclides of interest.

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A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Malidarre¹,

Akkurt²

2023

Preprint

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“…Thus besides other code it has been in a variety of studies in radiation fields [21][22][23][24][25][26][27][28][29][30][31][32][33][34][35][36][37][38][39]. In the present study, the FLUKA Monte Carlo Code is utilized to calculate the radiation shielding capacity of the HAP+ Fe2O3 samples [18,[40][41].…”

Section: Fluka Monte Carlo Code Environmentmentioning

confidence: 99%

Examining the HAP+ Fe2O3 Response in the Magnetic Field, Radiation Protection and Mechanical Properties

Malidarre

Akkurt²,

Korkmaz³

et al. 2023

Preprint

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HAP (Hydroxyapatite) bio-composite has been used extensively to repair and replace bone and teeth tissues in the human body. However, because of the poor mechanical features of HAP bio-composites, significant enhancements in the strength and toughness of pure HAP have been achieved by the insertion of various alloys and materials into HAP. Accordingly, the present study evaluates the radiation shielding and mechanical features of the Fe2O3 -reinforced HAP composite as an implant for 0.0, 2.5, 5.0, and 7.5 wt.% Fe2O3. Also, the composite response in a magnetic field has been investigated. Employing FLUKA Monte Carlo Code, radiation shielding factors are obtained. In addition, the mechanical characteristics of the studied composites are evaluated using the theoretical method. Findings reveal that increasing the Fe2O3 contents in HAP bio-composite enhances the preferred samples’ radiation shielding and mechanical qualities. Furthermore, in the absence of a magnetic field, the particles' spatial map exhibits symmetric behavior along the x-axis, however, a different trend is observed in the presence of a magnetic field with a value of Bx=5 microT.

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“…On the other hand the radiation requires extreme care due to its hazardous effect to human cell. Thus radiation dosimetry becomes important in science and new techniques, materials have been under study to develop as alternative to conventional materials [1][2][3][4][5][6][7][8][9][10][11]. The neutron with the proton is an important particle in nuclear physics and due to neutral character its shielding is more difficult than others.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Neutrons Shielding Properties for Some Medical Materials

WAHEED¹,

İmamoğlu

Karpuz

et al. 2022

International Journal of Computational and Experimental Science and Engineering

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Monte Carlo simulation study on TeO2–Bi2O–PbO–MgO–B2O3 glass for neutron-gamma 252Cf source

Cited by 68 publications

References 50 publications

A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Examining the HAP+ Fe2O3 Response in the Magnetic Field, Radiation Protection and Mechanical Properties

Simulation of Neutrons Shielding Properties for Some Medical Materials

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