• Nuclear Engineering and Technology
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• 제54권3호
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• pp.1062-1070
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• 2022

In the present communication, pure and stable α-Bismuth Oxide (Bi₂O₃) nanoparticles (NPs) were synthesized by low temperature solution combustion method using urea as a fuel and calcined at 500℃. The synthesized sample was characterized by using powder X-ray Diffraction (PXRD), Scanning Electron Microscopy (SEM), Energy dispersive X-ray analysis (EDAX), Transmission Electron Microscopy (TEM), Fourier Transform Infrared Spectroscopy (FTIR) and UV-Visible absorption spectroscopy. The PXRD pattern confirms the formation of mono-clinic, stable and low temperature phase α-Bi₂O₃. The direct optical energy band gap was estimated by using Wood and Tauc's relation which was found to be 2.81 eV. The characterized sample was studied for X-ray/gamma ray shielding properties in the energy range 0.081-1.332 MeV using NaI (Tl) detector and multi channel analyzer (MCA). The measured shielding parameters agrees well with the theory, whereas, slight deviation up to 20% is observed below 356 keV. This deviation is mainly due to the influence of atomic size of the target medium. Furthermore an accurate theory is necessary to explain the interaction of X-ray/gamma ray with the NPs.The present work opens new window to use this facile, economical, efficient, low temperature method to synthesize nanomaterials for X-ray/gamma ray shielding purpose.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.380-387
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• 2015

A lead slowing-down spectrometer (LSDS) system is a promising nondestructive assay technique that enables a quantitative measurement of the isotopic contents of major fissile isotopes in spent nuclear fuel and its pyroprocessing counterparts, such as $^{235}U$, $^{239}Pu$, $^{241}Pu$, and, potentially, minor actinides. The LSDS system currently under development at the Korea Atomic Energy Research Institute (Daejeon, Korea) is planned to utilize a high-flux ($>10^{12}n/cm^2{\cdot}s$) neutron source comprised of a high-energy (30 MeV)/high-current (~2 A) electron beam and a heavy metal target, which results in a very intense and complex radiation field for the facility, thus demanding structural shielding to guarantee the safety. Optimization of the structural shielding design was conducted using MCNPX for neutron dose rate evaluation of several representative hypothetical designs. In order to satisfy the construction cost and neutron attenuation capability of the facility, while simultaneously achieving the aimed dose rate limit (< $0.06{\mu}Sv/h$), a few shielding materials [high-density polyethylene (HDPE)eBorax, $B_4C$, and $Li_2CO_3$] were considered for the main neutron absorber layer, which is encapsulated within the double-sided concrete wall. The MCNP simulation indicated that HDPE-Borax is the most efficient among the aforementioned candidate materials, and the combined thickness of the shielding layers should exceed 100 cm to satisfy the dose limit on the outside surface of the shielding wall of the facility when limiting the thickness of the HDPE-Borax intermediate layer to below 5 cm. However, the shielding wall must include the instrumentation and installation holes for the LSDS system. The radiation leakage through the holes was substantially mitigated by adopting a zigzag-shape with concrete covers on both sides. The suggested optimized design of the shielding structure satisfies the dose rate limit and can be used for the construction of a facility in the near future.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.282-293
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• 2021

This paper examines gamma-ray shielding properties of SBC-Bx glass system with the chemical composition of 40SiO₂-10B₂O₃-xBaO-(45-x)CaO- yZnO- zMgO (where x = 0, 10, 20, 30, and 35 mol% and y = z = 6 mol%). Mass attenuation coefficient (µ/ρ) which is an essential parameter to study gamma-ray shielding properties was obtained in the photon energy range of 0.015-15 MeV using PHITS Monte Carlo code for the proposed glasses. The obtained results were compared with those calculated by WinXCOM program. Both the values of PHITS code and WinXCOM program were observed in very good agreement. The (µ/ρ values were then used to derive mean free path (MFP), electron density (N_eff), effective atomic number (Z_eff), and half value layer (HVL) for all the glasses involved. Additionally, G-P method was employed to estimate exposure buildup factor (EBF) for each glass in the energy range of 0.015-15 MeV up to penetration depths of 40 mfp. The results reveal that gamma-ray shielding effectiveness of the SBC-Bx glasses evolves with increasing BaO content in the glass sample. Such that SBC-B35 glass has superior shielding capacity against gamma-rays among the studied glasses. Gamma-ray shielding properties of SBC-B35 glass were compared with different conventional shielding materials, commercial glasses, and newly developed HMO glasse. Therefore, the investigated glasses have potential uses in gamma shielding applications.

• Journal of Radiation Protection and Research
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• 제47권3호
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• pp.152-157
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• 2022

Background: The hemi-body electron beam irradiation (HBIe^-) technique has been proposed for the treatment of mycosis fungoides. It spares healthy skin using an electron shield. However, shielding electrons is complicated owing to electron scattering effects. In this study, we developed a thimble-like head bolus shield that surrounds the patient's entire head to prevent irradiation of the head during HBIe^-. Materials and Methods: The feasibility of a thimble-like head bolus shield was evaluated using a simplified Geant4 Monte Carlo (MC) simulation. Subsequently, the head bolus was manufactured using a three-dimensional (3D) printed mold and Ecoflex 00-30 silicone. The fabricated head bolus was experimentally validated by measuring the dose to the Rando phantom using a metal-oxide-semiconductor field-effect transistor (MOSFET) detector with clinical configuration of HBIe^-. Results and Discussion: The thimble-like head bolus reduced the electron fluence by 2% compared with that without a shield in the MC simulations. In addition, an improvement in fluence degradation outside the head shield was observed. In the experimental validation using the inhouse-developed bolus shield, this head bolus reduced the electron dose to approximately 2.5% of the prescribed dose. Conclusion: A thimble-like head bolus shield for the HBIe^- technique was developed and validated in this study. This bolus effectively spares healthy skin without underdosage in the region of the target skin in HBIe^-.

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.2078-2084
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• 2020

Magnesium oxide (MgO) and Zinc oxide (ZnO) nanoparticles (NPs) have been successfully synthesized by solid-solid reaction method. The structural properties of ZnO and MgO NPs were studied using X-ray diffraction (XRD) and scanning electron microscopy (SEM). XRD results indicated a formation of pure MgO and ZnO NPs. The mean diameter values of the agglomerated particles were around to be 70 and 50 nm for MgO and ZnO NPs, respectively using SEM analysis. Further, a wide-range of nuclear radiation shielding investigation for gamma-ray and fast neutrons have been studied for Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. FLUKA and Microshield codes have been employed for the determination of mass attenuation coefficients (μ_m) and transmission factors (TF) of Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. The calculated values for mass attenuation coefficients (μ_m) were utilized to determine other vital shielding properties against gamma-ray radiation. Moreover, the results showed that Zinc oxide (ZnO) nanoparticles with the lowest diameter value as 50 nm had a satisfactory capacity in nuclear radiation shielding.

• 대한방사선치료학회지
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• 제12권1호
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• pp.85-90
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• 2000

• 한국산학기술학회논문지
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• 제11권3호
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• pp.1035-1039
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• 2010

고에너지 X-ray를 투시 방사선원으로 사용한 컨테이너 화물검색시스템에서 생성되는 광중성자에 의해 주변 콘크리트 차폐벽에서 발생되는 방사화생성물을 평가하였다. 몬테카를로 전산해석 코드인 MCNPX2.5.0을 사용하였으며, 참조시스템은 국내 주요 항만에 설치된 9MeV X-ray 고정식 양방향 컨테이너 화물검색시스템이다. 9MeV X-ray 조사에 따라 생성되는 광중성자의 (n,$\gamma$) 반응에 의한 방사화생성물 재고량을 계산하고 이에 따라 야기되는 방사선 피폭선량을 계산하였다.

• 한국방사선학회논문지
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• 제9권7호
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• pp.459-465
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• 2015

PET/CT에서 사용되는 511 keV ${\gamma}$선의 납 차폐체 사용 유 무에 따른 에너지 흡수 분포를 몬테카를로 모의 모사를 통해 평가하였다. 실험은 ICRU Slab 팬텀을 이용하여 깊이에 따라 피부표면(0.07), 수정체(3), 심부(10)에 대해 실험을 진행하였으며, 납 두께에 따른 에너지 흡수 분포 차이와 납과 팬텀의 거리에 따른 공기층의 영향에 대해 분석 하였다. 그 결과 납 차폐체 사용 시 산란전자선에 의해 피부표면에 에너지 흡수 분포가 높게 나타났다. 산란전자선선은 납과 팬텀 사이의 거리가 증가함에 따라 점차 제거되었으며, 0.25 mm 납 차폐체 사용 시 9 cm 이상의 공기층이 있어야 피부표면의 도달하는 산란전자선의 영향을 방지 할 수 있었다. 또한 0.5 mm의 납 차폐체 사용 시 1 cm 이상의 공기층이 있어야 피부표면에 도달하는 산란전자선의 영향을 방지 할 수 있었으며, 공기층을 고려하지 않을 경우 0.75 mm이상의 납 두께를 사용하여야 피부표면의 산란전자선의 영향을 방지 할 수 있다.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2025-2037
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• 2021

The influence of lead cations on natural quartz (QZ) from Egypt as a glass shielding material for the composition with nominal formula (10Na₂O - (90 - x) QZ - xPbO (where x = 30, 35, 40, 45 and 50 mol %)) was examined. The studied samples are synthesized via the melt quenching method at 1050 ℃. The X-ray diffraction XRD patterns were confirmed the glass nature for studied samples. Moreover, the optical properties, and the transparency for all compositions were examined by UV-Vis spectroscopy. Also, the major elemental composition of the natural quartz were estimated via the X-ray fluorescence (XRF) technique. Further, the density and molar volume were determined. Furthermore, the nuclear shielding parameters such as, mass attenuation coefficient, effective atomic number, electronic density, the total atomic, and electronic cross sections as well as the mean free path, and the half value layer with different gamma ray energies (81 keV-1407 keV) were calculated. Besides, the results showed that the shielding behavior towards the gamma ray radiation for all glass samples was increased as the increment in PbO concentration in the glass system.

• 한국산학기술학회논문지
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• 제18권2호
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• pp.95-101
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• 2017

본 논문에서는 복합재료로 만들기 위한 전처리 단계에서 수행한 사이징 제거 상태를 영상처리 알고리즘을 적용하여 수치적으로 나타내었고, 전자파 차폐 성능을 높이기 위해서 건식 공정 방식으로 니켈도금 탄소섬유를 제작하였다. 탄소섬유 제조에서 폴리머 종류로 감싸져 나온 사이징은 건식 코팅을 위해서는 제거해야 한다. 사이징이 제거된 상태를 주사 전자현미경(scanning electron microscope, SEM)으로 촬영한 이미지에서 탄소 섬유의 규칙적인 패턴, 즉 상관성을 구함으로써 수치적인 값으로 나타낼 수 있다. 사이징의 제거 방식은 용액, 압축 공기와 용액과 압축공기(하이브리드)로 제거한 SEM 영상에 대하여 제안된 방법을 적용한 결과 하이브리드 방식이 우수함을 확인 할 수 있었다. 그리고 사이징이 제거된 스프레딩 탄소 섬유 롤을 롤투롤 스퍼터 방식으로 니켈도금 탄소 섬유를 제작할 수 있었다. 제작된 30um, 40um과 100um 니켈코팅 탄소섬유에 대해서 전자파 차폐 성능을 측정하였다. 한국산업기술시험원에서 100um 니켈코팅 탄소섬유의 전자파 차폐 성능을 평가한 결과 최저 66.7(dB)에서 최고 73.2(dB)의 전자파 차폐 성능을 보였다. 이것은 구리의 전자파 차폐율과 유사하여 EV/HEV자동차의 케이블로 사용될 수 있다.