• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.539-540
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• 2018

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.1943-1949
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• 2024

This study focuses on the comparative analysis of ABS polymer samples produced using two distinct manufacturing techniques: 3D printing and the sol-gel methods. In the first approach, ABS polymer was augmented with rare earth oxides, Er₂O₃ and Gd₂O₃, in nano powder form and fabricated into test specimens using 3D printing technology. In the second approach, identical samples were prepared via the sol-gel technique involving mold-based fabrication. Elemental content analysis revealed no significant differences between the samples produced by the two methods. The study proceeds to evaluate the gamma-ray shielding, neutron shielding, temperature resistance, and SEM/EDS pictures of ABS samples generated through both techniques. 3D printing method exhibited more favorable results in terms of structure morphology and thermal stability while there is no significant difference for radiation shielding. The results provide insights into the performance and suitability of each production method for radiation shielding applications. This research not only contributes to enhancing radiation shielding technology but also informs the selection of the most appropriate fabrication method for specific applications in nuclear technologies and diagnostic energy range in medical purposes.

• Nuclear Engineering and Technology
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• 제51권6호
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• pp.1633-1637
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• 2019

While considering the photon attenuation coefficient (${\mu}$) and its related parameters for photons shielding, it is necessary to account for its transmitted and reflected photons energy spectra and dose contribution. Monte Carlo simulation was used to study the efficiency of clay ($1.99g\;cm^{-3}$) as a shielding material below 150 keV photon. Am-241 gamma source and an X-ray of 150 kVp were calculated. The calculated value of ${\mu}$ for Am-241 is higher within 5.61% compared to theoretical value for a single-energy photon. The calculated half-value layer (HVL) is 0.9335 cm, which is lower than that of ordinary concrete for X-ray of 150 kVp. A thickness of 2 cm clay was adequate to attenuate 90% and 85% of the incident photons from Am-241 and X-ray of 150 kVp, respectively. The same thickness of 2 cm could shield the gamma source dose rate of Am-241 (1 MBq) down to $0.0528{\mu}Sv/hr$. For X-ray of 150 kVp, photons below 60 keV were significantly decreased with 2 cm clay and a dose rate reduction by ~80%. The contribution of reflected photons and dose from the clay is negligible for both sources.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3051-3058
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• 2022

In the present work, untreated Iraqi sand with grain sizes varied between 100 and 200 ㎛ was used to produce a colored glass sample that has shielding features against the low gamma-ray energy. Therefore, a weight of 70-60 wt % sand was mixed with 9-14 wt% B₂O₃, 8-10 wt% Na₂O, 4-6 wt% of CaO, 3-6 wt% Al₂O₃, in addition to 0.3% of Co₂O₃. After melting and annealing the glass sample, the X-ray diffraction spectrometry was applied to affirm the amorphous phase of the fabricated glass samples. Moreover, the X-ray dispersive energy spectrometry was used to measure the chemical composition, and the MH-300A densimeter was applied to measure the fabricated sample's density. The Makishima-Makinzie model was applied to predict the mechanical properties of the fabricated glass. Besides, the Monte Carlo simulation was used to estimate the fabricated glass sample's radiation shielding capacity in the low-energy region between 22.1 and 160.6 keV. Therefore, the simulated linear attenuation coefficient changed between 10.725 and 0.484 cm^-1, raising the gamma-ray energy between 22.1 and 160.6 keV. Also, other shielding parameters such as a half-value layer, pure lead equivalent thickness, and buildup factors were calculated.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2016년도 추계학술대회
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• pp.948-949
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• 2016

본 논문에서는 감마선원 영상화를 위한 감마선 탐지장치에 적용할 차폐체의 구조 변경에 대한 연구를 수행하였다. 선행 연구를 통해 상용 감마선 영상화 장치의 차폐체와 차폐효율은 유사하지만 경량화 그리고 무게중심을 이동시킨 차폐체를 구현하였다. 본 논문에서는 모션 제어장치의 효율적인 동작을 위해 차폐체를 변경하였다. 차폐체 설계를 위해서 MCNP 전산모사를 수행하였으며, 그 결과 약 15%의 경량화 및 무게중심을 차폐체 중심으로 이동시키는 결과를 얻었다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2324-2331
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• 2024

The current study investigated Saudi Arabian oil fly ash impacts on Egyptian clay bricks' structural and radiation shielding properties. To produce the required bricks, crushed clay minerals from the Hafafit area were mixed with 0, 10, 20, 30, and 40 % wt.% Saudi Arabian oil fly ash and pressed at a pressure rate of 68.55 MPa. Identification of the minerals in the chosen clay was achieved via X-ray diffraction. Additionally, the material's morphology and chemical composition were determined through scanning electron microscope and energy-dispersive X-ray. The fabricated bricks' density was reduced by 36.3 % through increasing the concentration of fly ash from 0 to 40 wt%. Then, the fly ash addition's influence on the fabricated clay bricks' γ-ray shielding properties was investigated by Monte Carlo simulation, which found a reduction in the fabricated bricks' linear attenuation coefficient (LAC) by 41.2, 36.0, 33.8, and 33.8 % at the 0.059, 0.103, 0.662, and 1.252 MeV γ-ray energies, respectively. The LAC reduction caused an increase in the fabricated bricks' half-value thickness, transmission factor, and the equivalent thickness of the lead. Moreover, the thicker fabricated sample thicknesses were found to have high γ-ray shielding capacity and can thus be used in radiation shielding applications.

• Nuclear Engineering and Technology
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• 제51권3호
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• pp.860-866
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• 2019

The lead element or its salts are good radiation shielding materials. However, their toxic effects are high. Due to less toxicity of bismuth salts, the radiation shielding properties of the bismuth salts have been investigated and compared to that of lead salts to establish them as a better alternative to radiation shielding material to the lead element or its salts. The transmission geometry was utilized to measure the mass attenuation coefficient (${\mu}/{\rho}$) of different salts containing lead and bismuth using a high-resolution HPGe detector and different energies (between 81 and 1333 keV) emitted from point sources of $^{133}Ba$, $^{57}Co$, $^{22}Na$, $^{54}Mn$, $^{137}Cs$, and $^{60}Co$. The experimental ${\mu}/{\rho}$ results are compared with the theoretical values obtained through WinXCOM program. The theoretical calculations are in good agreement with their experimental ones. The radiation protection efficiencies, mean free paths, effective atomic numbers and electron densities for the present compounds were determined. The bismuth fluoride ($BiF_3$) is found to have maximum radiation protection efficiency among the selected salts. The results showed that present salts are more effective for reducing the intensity of gamma photons at low energy region.

• Nuclear Engineering and Technology
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• 제51권7호
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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.

• Journal of Radiation Protection and Research
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• 제19권1호
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• pp.13-22
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• 1994

CANDU 6 중수형 원자로 운전중에 Calandria Shell내에서 발생하는 $(n,\;{\gamma})$ 반응유발 열중성자속분포와 CANDU 6 발전소의 측면 및 하단 차폐구조에서의 방사선 선량률을 계산하기 위하여 몬테칼로 방법을 이용한 MCNP 4.2 코드를 사용하였다. 계산결과, Mainshell, Annular Plate와 Subshell내 의 열중성자속분포는 $10^{11}{\sim}10^{13}\;neutrons/cm^2-sec$로 나타났고, 이는 DOT 4.2 코드의 계산결과와 비교해 볼 때 약간 큰 값들의 분포를 보여주고 있다. 이 계산결과의 응용으로서 작업자 접근가능지역 (Worker Accessible Areas)에서의 감마선량률을 계산해본 결과 설계목표치인 $6{\mu}Sv/h$보다 낮은 값을 주는 것으로 나타났다. $(n,\;{\gamma})$ 반응유발 열중성자속분포에 대한 MCNP 4.2 코드의 계산결과는 CANDU 6형 원자로의 방사선 차폐해석에 중요한 자료로 널리 이용될 수 있을 것이다.

• 한국산학기술학회논문지
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• 제19권9호
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• pp.124-129
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• 2018

본 연구는 Apron의 재질로 이용되고 있는 텅스텐 차폐체를 핵의학과에서 사용하는 선원의 종류와 차폐체의 두께, 선원부터 검출기 사이의 거리를 변화시켜 차폐체에 투과시킨 후 투과선량과 차폐율을 알아보고자 하였다. 실험을 위해서 선원과 차폐체와 검출기를 일직선으로 배치하고 높이 100 cm 지점에서 Inspector로 측정하였다. 그 결과 텅스텐에 차폐효과가 가장 높은 선원은 $^{201}Tl$ 선원으로 측정되었고, $^{123}I$ 선원이 $^{99m}Tc$ 선원보다 차폐효과가 높게 나타났다. 실험에 사용한 선원과 검출기 사이의 거리는 멀어질수록 투과선량은 작아졌고, 텅스텐 차폐체의 두께는 두꺼울수록 차폐율은 높게 측정되었다. 하지만 $^{131}I$와 $^{18}F$ 선원에서는 0.25 mmPb의 차폐체를 사용했을 경우 차폐체가 없을 경우 보다 차폐율이 감소하는 것을 확인하였다. 따라서 $^{13}1I$와 $^{18}F$ 선원을 사용할 경우에는 방사선 차폐효과가 높은 텅스텐일지라도 선원의 종류에 따른 특성과 차폐체의 두께를 고려하여 사용하길 권장하고, 실험 결과를 참고하여 사용한다면 피폭 저 감화방안에 도움을 줄 수 있을 것으로 생각된다.