• Title/Summary/Keyword: Gamma ray shielding

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Shielding Analysis of the Material and Thickness of Syringe Shield on the Radionuclide (방사성 핵종별 주사기 차폐기구의 재질 및 두께에 대한 차폐분석)

  • Cho, Yong-In;Kim, Chang-Soo;Kang, Se-Sik;Kim, Jung-Hoon
    • The Journal of the Korea Contents Association
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    • v.15 no.7
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    • pp.282-288
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    • 2015
  • A monte carlo simulation about shielding material and thickness of the syringe shield for radiation shield was performed. As a result of analysis, high atomic number materials such as tungsten, lead and bismuth have the highest shielding effect. However, $^{18}F$, $^{67}Ga$ and $^{111}In$ show high energy distribution in the region with thin shielding thickness. As the thickness of shielding materials increased, the energy distribution decreased due to reduction of ${\gamma}$-ray. In the case of low atomic number materials, they, showed energy distribution from highest to lowest, were barium sulfate, steel, stainless, iron and copper. Aluminum, plastic, concrete and water showed diverse aspect. they showed relatively high energy distribution because of increased ${\gamma}$-ray that penetrate the shield.

Investigation of photon, neutron and proton shielding features of H3BO3-ZnO-Na2O-BaO glass system

  • Mhareb, M.H.A.;Alajerami, Y.S.M.;Dwaikat, Nidal;Al-Buriahi, M.S.;Alqahtani, Muna;Alshahri, Fatimh;Saleh, Noha;Alonizan, N.;Saleh, M.A.;Sayyed, M.I.
    • Nuclear Engineering and Technology
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    • v.53 no.3
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    • pp.949-959
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    • 2021
  • The current study aims to explore the shielding properties of multi-component borate-based glass series. Seven glass-samples with composition of (80-y)H3BO3-10ZnO-10Na2O-yBaO where (y = 0, 5, 10, 15, 20, 25 and 30 mol.%) were synthesized by melt-quench method. Various shielding features for photons, neutrons, and protons were determined for all prepared samples. XCOM, Phy-X program, and SRIM code were performed to determine and explain several shielding properties such as equivalent atomic number, exposure build-up factor, specific gamma-ray constants, effective removal cross-section (ΣR), neutron scattering and absorption, Mass Stopping Power (MSP) and projected range. The energy ranges for photons and protons were 0.015-15 MeV and 0.01-10 MeV, respectively. The mass attenuation coefficient (μ/ρ) was also determined experimentally by utilizing two radioactive sources (166Ho and 137Cs). Consistent results were obtained between experimental and XCOM values in determining μ/ρ of the new glasses. The addition of BaO to the glass matrix led to enhance the μ/ρ and specific gamma-ray constants of glasses. Whereas the remarkable reductions in ΣR, MSP, and projected range values were reported with increasing BaO concentrations. The acquired results nominate the use of these glasses in different radiation shielding purposes.

Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code

  • Mahmoud, K.A.;Sayyed, M.I.;Tashlykov, O.L.
    • Nuclear Engineering and Technology
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    • v.51 no.7
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    • pp.1835-1841
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    • 2019
  • The mass attenuation coefficient ${\mu}_m$ for eight rock samples having different chemical composition was simulated using the MCNP 5 code in energy range($0.002MeV{\leq}E{\leq}10MeV$). Moreover, the ${\mu}_m$ for the studied rock samples was computed theoretically using XCOM database. The comparison between simulated and computed data for all selected rock samples showed a good agreement with differences varied between 0.01 and 8%. The highest ${\mu}_m$ was found for basalt rocks M2 and M1 and the lowest one is reported for limestone rocks Dike. The simulated values of the ${\mu}_m$ then were used to calculate other important shielding parameters such as the mean free path, effective electron density and effective atomic number. The exposure buildup factor EBF was also computed for the selected rocks with the contribution of G-P fitting parameters and the highest EBF attended by the basalt sample Sill and varied between 1.022 and 744 in the energy range between ($0.015MeV{\leq}E{\leq}15MeV$) but the lowest EBF achieved by basalt sample M2 and varied between 1.017 and 491 in the same energy range.

Enhancement and optimization of gamma radiation shielding by doped nano HgO into nanoscale bentonite

  • Allam, Elhassan A.;El-Sharkawy, Rehab M.;El-Taher, Atef;Shaaban, E.R.;RedaElsaman, RedaElsaman;Massoud, E. El Sayed;Mahmoud, Mohamed E.
    • Nuclear Engineering and Technology
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    • v.54 no.6
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    • pp.2253-2261
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    • 2022
  • In this study, nano-scaled shielding materials were assembled and fabricated by doping different weight percentages of Nano-mercuric oxide (N-HgO) into Nano-Bentonite (N-Bent) based on using (100-x% N-Bent + x% N-HgO, x = 10, 20, 30, and 40 wt %). The fabricated N-HgO/N-Bent nanocomposites were characterized by FT-IR, XRD, and SEM and evaluated to evaluate their shielding properties toward gamma radiation by using four different γ-ray energies form three point sources; 356 keV from 133Ba, 662 keV from 137Cs as well as 1173, and 1332 keV from 60Co. The γ-rays mass attenuation coefficients were plotted as a function of the doped N-HgO concentrations into N-HgO/N-Bent nanocomposites. The computed values of mass attenuation coefficients (µm), effective atomic number (Zeff) and electron density (Nel) by the as-prepared samples were found to increase, while the half value layer (HVL) and mean free path (MFP) were identified to decrease upon increasing the N-HgO contents. It was concluded also that the increase in N-HgO concentration led to a direct increase in the mass attenuation coefficient from 0.10 to 0.17 cm2/g at 356 keV and from 0.08 to 0.09 cm2/g at 662 keV. However, a slight increase was observed in the identified mass attenuation coefficients at (1172 and 1332 keV).

A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxide

  • Hammam Abdurabu Thabit;Abd Khamim Ismail;N.N. Yusof;M.I. Sayyed;K.G. Mahmoud;I. Abdullahi;S. Hashim
    • Nuclear Engineering and Technology
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    • v.55 no.5
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    • pp.1734-1741
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    • 2023
  • This work presents the synthesis and preparation of a new glass system described by the equation of (70-x) B2O3-5TeO2 -20SrCO3-5ZnO -xBi2O3, x = 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 ℃. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi2O3 content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi2O3 is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi2O3 has good shielding properties in low, intermediate, and high energy intervals.

SIMULATION OF SHIELDING EFFECTS ON THE TOTAL DOSE OBSERVED IN TDE OF KITSAT-1 (KITSAT-1 TDE의 차폐 효과에 의한 총 축적 방사능양 변화에 대한 연구)

  • 김성준;신영훈;민경욱
    • Journal of Astronomy and Space Sciences
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    • v.18 no.1
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    • pp.71-80
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    • 2001
  • The threshold voltage shift observed in TDE (Total Dose Experiment) on board the KITAT-1 is converted into dose (rad($SiO_2$)) using the result of laboratory calibration with Co-60 gamma ray source in KAERI (Korea Atomic Energy Research Institute). Simulation using the NASA radiation model of geomagnetosphere verifies that the dose difference between RADFET1 and RADFET3 observed on KITSAT-1 comes from the difference in shielding thickness at the position of these RADFETs.

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Characterization and experimental investigation for gamma-ray shielding competence of basalt-doped polyethylene nanocomposites

  • I.A. El-Mesady;F.I. El-Agawany;H. El-Samman;Y.S. Rammah;A. Hussein;R.A. Elsad
    • Nuclear Engineering and Technology
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    • v.56 no.2
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    • pp.477-484
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    • 2024
  • Experimental investigations on gamma - rays attenuation parameters and dielectric spectroscopic properties were done on a polymeric mixture with chemical composition (100-x) polyethylene + x basalt, where x = 0, 1, 3, 5, 10, and 20 wt%. Using the melting blending technique,six nanocomposite polymeric samples were prepared. The linear attenuation coefficient µ of each prepared set of samples was measured using a gamma-ray spectrometer including High Purity Germanium detector (HPGe) at energies 662.5, 1173.24, and 1332.51 keV. Based on the measured values of (µ) and sample density, the other effective shielding parameters were calculated. The values of µ showed an increase with increasing the dopant ratios from 0.0 up to 20.0 wt%. In addition, the µ values decreased with the photon's energy. The µ values were found 0.0847 up to 0.1175 cm-1, 0.0571 up to 0.0855 cm-1, and 0.0543 up to 0.075 cm-1 at 662.5, 1173.24, and 1332.51 keV. for B0 up to B20, respectively. The ATR spectroscopy was done on the prepared samples, and a good evidence of adding the filler to the pure polyethylene (HDPE) was obtained. Besides, an enhancement in dielectric constant by insertion of basalt NPs also recorded and can be attributed to the large dielectric constant of basalt compared to pure HDPE.

Effect of the new photoatomic data library EPDL2017 to mass attenuation coefficient calculation of materials used in the nuclear medicine facilities using EpiXS software

  • Jecong, J.F.M.;Hila, F.C.;Balderas, C.V.;Guillermo, N.R.D.
    • Nuclear Engineering and Technology
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    • v.54 no.9
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    • pp.3440-3447
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    • 2022
  • The accuracy of the photoatomic cross-section data is of great importance in the field of radiation protection, particularly in the characterization of radiation shielding materials. With the release of the latest and probably the most accurate photoatomic data library, EPDL2017, the need to re-evaluate all the existing and already established mass attenuation coefficients (MACs) of all radiation shielding materials arises. The MACs of several polymers, alloy-based, glasses, and building materials used in a nuclear medicine facility were investigated using the EPDL2017 library embedded in EpiXS software and were compared to MACs available in the literature. The relative differences between MACEpiXS and MACXCOM were negligible, ranging from 0.02% to 0.36% for most materials. However, for material like a glass comprising of elements Te and La evaluated near their corresponding K-edge energies, the relative differences in MACs increased up to 1.46%. On the other hand, a comparison with MACs calculated based on EPDL97 (a predecessor of EPDL2017) revealed as much as a 6.61% difference. Also, it would seem that the changes in MACs were more evident in the materials composed of high atomic number elements evaluated at x-ray energies compared to materials composed of low atomic number elements evaluated at gamma-ray energies.

Gamma Radiation Shielding Effect of Various Heavy Concretes Using Domestic Mineral Aggregates

  • Lim, Yong-Kyu
    • Nuclear Engineering and Technology
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    • v.2 no.3
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    • pp.149-161
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    • 1970
  • This paper describes a detailed investigational performance on the gamma radiation shield effect of heavy concretes that were manufactured by the use of mineral ores produced domestically and which may be possibly applied for the biological shield design. Ten different kinds of mineral ores were collected for use as the aggregates, physical test and chemical analysis for them were carried out to select the aggregate with a better property. Through the experimental investigation on the shielding effect of various concretes with different combination of concrete components such as water-cement and fine-coarse aggregate ratios, it was possible to derive some criteria for the best condition being capable of obtaining the concretes with high density and good uniformity. Data on the shielding-effectiveness of the different concretes were obtained by performing collimated beam experiment using 60Co gamma-ray. Analyzing the shielding-efficiency, shielding-concrete specific gravity and biological shield cost, the optimum condition of yielding the best economic shielding design, with low cost and good spatial distribution to some extent was determined.

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Development of high-performance heavy density concrete using different aggregates for gamma-ray shielding

  • Ouda, Ahmed S.
    • Advances in materials Research
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    • v.3 no.2
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    • pp.61-75
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    • 2014
  • This study aimed to investigate the suitability of some concrete components for producing "high-performance heavy density concrete" using different types of aggregates that could enhances the shielding efficiency against ${\gamma}$-rays. 15 mixes were prepared using barite, magnetite, goethite and serpentine aggregates along with 10% silica fume, 20% fly ash and 30% blast furnace slag to total OPC content for each mix. The mixes were subjected to compressive strength at 7, 28 and 90 days. In some mixes, compressive strengths were also tested up to 90 days upon replacing sand with the fine portions of magnetite, barite and goethite. The mixes containing magnetite along with 10% SF reaches the highest compressive strength exceeding over M60 requirement by 14% after 28 days. Whereas, the compressive strength of concrete containing barite was very close to M60 and exceeds upon continuing for 90 days. Also, the compressive strength of high-performance concrete incorporating magnetite fine aggregate was significantly higher than that containing sand by 23%. On the other hand, concrete made with magnetite fine aggregate had higher physico-mechanical properties than that containing barite and goethite. High-performance concrete incorporating magnetite fine aggregate enhances the shielding efficiency against ${\gamma}$-rays.