• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1323-1330
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• 2021

This work reported the radiation shielding characteristic of the bismuth titanium vanadium sodium tellurite glass system. The density of the specially-developed glass samples was increased from 2.21 to 4.01 g/cm³ with the addition of Bi₂O₃, despite the fact the molar volume is decease within 85.43-54.79 cm³/mol. The WinXcom program was used to approximate the effect of Bi₂O₃ on the gamma radiation shielding parameters of bismuth titanium vanadium sodium tellurite glasses. The ㎛ values decrease with the increase of Bi₂O₃ concentration. The computed data shows that the glass sample with 20 mol.% of Bi₂O₃ content has the greatest radiation attenuation performance in comparison to other selected glasses. The Bi₂O₃-TiO₂-V₂O₅-Na₂O-TeO₂ glass system shows excellent neutron shielding material with high long-term light transmittance and discharge resistance and could be potentially used as transparent radiation-resistant shielding glass applications.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.100-105
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• 2024

In this study, we propose an alternative approach using Artificial Neural Networks (ANN) for determining Mass Attenuation Coefficients (MAC) in various glass systems. This method takes into account the weights of glass compositions, density, and photon energy as input features. The ANN model was trained and tested on a dataset consisting of 650 data points and subsequently validated through a K-fold cross-validation procedure. Our findings demonstrate a high level of accuracy, with R² values ranging from 0.90 to 0.99. Additionally, the model exhibits robust extrapolation capabilities with an R² score of 0.87 for predicting MAC values in a new glass system. Furthermore, this approach significantly reduces the need for costly and time-consuming computations and experiments, making it a potential tool for selecting materials for effective radiation protection.

• Nuclear Medicine and Molecular Imaging
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• 제42권2호
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• pp.112-117
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• 2008

Artifact corrections including normalization and attenuation correction were important for quantitative analysis in Nuclear Medicine Imaging. Normalization is the process of ensuring that all lines of response joining detectors in coincidence have the same effective sensitivity. Failure to account for variations in LOR sensitivity leads to bias and high-frequency artifacts in the reconstructed images. Attenuation correction is the process of the correction of attenuation phenomenon lies in the natural property that photons emitted by the radiopharmaceutical will interact with tissue and other materials as they pass through the body. In this paper, we will review the several approaches for normalization and attenuation correction strategies.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2607-2612
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• 2020

The present work was aimed to show the possibility of using hydrogel (acrylic/boric acid) for evaluation of the neutron radiation shielding. The influence of acrylic acid concentration, different gamma doses and relative contents of boric acid were studied. The physical properties and the thermomechanical stability of the studied samples were investigated. The shielding property of the composite for neutron was tested by Pu-Be neutron source (5 Ci) under room temperature. The neutron fluence rates and gamma fluxes were measured using a stilbene organic scintillator. The macroscopic effective removal cross-section Σ_R (cm^-1) of fast neutrons and total attenuation coefficient μ (cm^-1) of gamma rays has been studied experimentally. The transmission parameters, the relaxation length (??) and the half-value layer (HVL) were obtained. The obtained results indicated that the addition of boric acid to acrylic acid tends to increase the macroscopic effective removal cross-section Σ_R (cm^-1) to 0.141 compared to 0.094 of ordinary concrete.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4142-4149
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• 2021

In the radiation protection application, the metal-polymer composites have been developed for their radiation shielding properties. In this research, the elastomer composites doped by 10 ㎛ and 100nm size of lead, bismuth and tungsten particles as filler with 30 and 60 wt percentages were prepared. To survey the shielding properties of the polymer composites using gamma-ray emitted from 152Eu and 137Cs sources, the gamma flux was measured by using NaI(Tl) detector, then the linear attenuation coefficient was calculated. Also, the Monte Carlo simulation (MCs) method was used. The results showed a direct relationship between the linear attenuation coefficients of the absorbent and filler ratio. Also, the decrease in the particle size of the shielding material in each weight percentage improved the radiation shielding features. When the dimension of the particles was in the order of nano-size, more attenuation was achieved. At low energies used for medical diagnostic X-ray applications due to the predominance of the photoelectric effect, bismuth and lead were suitable selection as filler.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.666-672
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• 2024

In the present work, a new brick series based on the Vietnamese white clay minerals from the Bat Trang was fabricated to be applied in the radiation protection applications during the decommissioning of the nuclear power reactors. The bricks were constructed under various pressure rates varied from 7.61 MPa to 114.22 MPa. The influence of pressure rate on the physical and γ-ray shielding properties were investigated in the study. The experimental measurement for the material's density using the MH-300A density meter showed an enhancement in the prepared bricks' density by 22.5 % with increasing the applied pressure rate while the bricks' porosity reduced by 31.2 % when the pressure rate increased from 7.61 MPa to 114.22 MPa. The increase in the fabricated bricks density and the reduction in their porosities enhances the bricks' linear attenuation coefficients as measured by the NaI (Tl) detector along the energy range extended from 0.662 MeV to 1.332 MeV. The linear attenuation coefficient increased by 13.8 %, 17.6 %, 17.0 %, and 17.1 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively. The enhancement in the linear attenuation coefficient increases the bricks' radiation protection efficiency by 10.22 %, 14.48 %, 14.09 %, and 14.26 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively.

• 한국방사선학회논문지
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• 제17권4호
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• pp.489-495
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• 2023

방사선 방어시설은 진단용 방사선 발생장치가 설치되어 있는 장소에 구축되어 환자, 방사선 작업 종사자 등의 피폭을 방지한다. 본 연구에서는 이러한 방사선 방어시설의 주 재료인 납에 대해 최대관전압별 차폐 두께의 경향성을 몬테칼로 시뮬레이션과 실측을 통해 비교 검증하고자 한다. 몬테칼로 시뮬레이션 코드 중 Monte Carlo N-Particle 6를 활용하였으며 해당 시뮬레이션 상에 모사한 납 차폐 구조도는 선원과 납 시트 사이의 거리는 100 cm, 조사야 크기는 10 × 10 cm²이며 관전압은 80, 100, 120, 140 kVp로 설정하였다. 각 관전압별 에너지 스펙트럼을 산출하여 시뮬레이션에 적용하였다. 80, 100, 120, 140 kVp별 각각 50, 70, 90, 95% 차폐율을 보이는 납 두께를 산출하였다. 80 kVp에서 각 차폐율에 해당하는 두께는 각각 0.03, 0.08, 0.2 1, 0.33 mm이며, 100 kVp에서는 0.05, 0.12, 0.30, 0.50 mm, 120 kVp에서는 0.06, 0.14, 0.38, 0.56 mm, 140 kV p에서는 0.08, 0.16, 0.42, 0.61 mm로 나타났다. 산출된 납 두께에 대해 실측을 진행하였으며 사용된 방사선 발생장치는 GE Healthcare 사의 Discovery XR 656이며 선량계측기의 경우 IBA 사의 MagicMax이다. 실측결과 80 kVp에서 각 두께별 차폐율은 43.56, 70.33, 89.85, 93.05%였으며 100 kVp에서는 52.49, 72.26, 86.31, 92.17%, 120 kVp에서는 48.26, 71.18, 87.30, 91.56%, 140 kVp에서는 50.45, 68.75, 89.95, 91.65%.로 나타났다. 시뮬레이션과 실측을 비교한 결과 두 값의 차이가 평균 약 3% 이내로 작은 것으로 확인되었다. 본 연구의 결과는 몬테칼로 시뮬레이션의 신뢰성을 검증함과 동시에 향후 방사선 방어시설의 구축에 있어 기초 데이터로 활용될 수 있을 것으로 사료된다.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 1999년도 추계종합학술대회
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• pp.462-466
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• 1999

고속 광대역 통신의 구현을 위하여 사용 주파수 대역이 밀리미터파 대에 근접함에 따라 마이크로파 신호 채널의 감쇠 특성을 고려한 필요성이 더욱 증대되고 있으며, 특히 B-WLL 시스템에 사용되는 27GHz 대역에서의 마이크로파 채널에 대하여는 강우감쇠로 인한 출력 보상을 반드시 고려하여야 한다. 그러나 어느 한 셀을 설계하면서 강우 감쇠를 고려하여 지나치게 방사 전력을 증가시키면 다른 셀의 수신장치에 간섭을 유발할 수 있다. 본 논문에서는 B-WLL 시스템의 주요 특성 및 인접 셀의 간섭으로 인하여 시스템 성능을 저하시키지 않을 정도로 전파신호 출력을 보상할 경우 적정한 셀 서비스 반경, 서비스 가능한 폭우의 한계 및 적응형 출력 제어 시스템에 대하여 고찰하였다.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.701-708
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• 2022

The mass attenuation coefficients (μ_m) of polyethylene glycol (PEG) of different molecular weights (1000-200,000) were measured using single-beam photon transmission. The X-ray fluorescent (XRF) photons from Zinc (Zn), Zirconium (Zr), Molybdenum (Mo), Silver (Ag) and Cadmium (Cd) targets were used to determine the attenuation of gamma radiation of energy range between 8.67 and 23.19 keV in PEG samples. The results were compared to theoretical values using XCOM and Monte Carlo simulation using Geant4 toolkit which was developed to validate the experiment at those certain energies. The mass attenuation coefficients were then used to compute the effective atomic numbers, electron density and half value layers for the studied samples. The outcomes showed good agreement between experimental and simulated results with those calculated theoretically by XCOM within 5% deviation. The PEG 1000 sample showed slightly higher μ_m value compared with the other samples. The dependence of the photon energy and PEG composition on the values of μ_m and HVL were investigated and discussed. In addition, the values of Z_eff and N_eff for all PEG samples behaved similarly in the given photon energy range, and they decreased as the photon energy increased.

• Radiation Oncology Journal
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• 제25권2호
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• pp.118-124
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• 2007

목 적: 투과성 필터를 이용하여 방사선치료를 받은 부비동 및 비암 환자에서 생존율 및 치료실패 양상을 분석하여 향후 치료계획을 할 때 도움을 주고자 한다. 대상 및 방법: 1992년 2월부터 2002년 3월까지 계명대학교 동산의료원 방사선종양학과에서 부비동 및 비암으로 진단받고 투과성 필터를 이용하여 방사선치료를 받은 환자 17명을 대상으로 후향적 분석을 시행하였다. 대상환자의 성별분포는 남자가 9명, 여자가 8명이었으며 연령분포는 $40{\sim}75$세(중앙값 59세)였다. 비강암이 7명, 부비동암이 10명이었고 조직학적으로 편평상피세포암이 11명, 선양낭성암종이 4명, 후신경모세포종이 2명이었다. AJCC 병기에 따라 II기가 3명, III기가 7명, IV기가 7명이었다. 방사선치료단독은 5명, 수술 후 방사선치료를 받은 환자는 12명이었다. 방사선치료는 일회 $1.8{\sim}2.0\;Gy$로 총 $44{\sim}76\;Gy$ (중앙값 60 Gy)를 조사하였다. 추적관찰기간은 $3{\sim}173$개월(중앙값 78개월)이었다. 결 과: 2년 생존율과 무병생존율은 76.4%이었고 5년, 10년 생존율은 각각 76.4%, 45.6%, 5년, 10년 무병생존율은 70.6%이었다. 수술유무에 따른 5년 무병생존율은 수술을 시행한 군은 91.6% 수술을 시행하지 않은 환자군은 20%로 통계적으로 유의하게 차이가 있었다(p=0.006). 병리 형태나 병기에 따른 생존율의 차이는 없었다. 5명(29%)의 국소재발률을 보였으며 원격전이는 없었고 수술을 요하는 심각한 부작용은 없었다. 결 론: 부비동 및 비암에서 투과성 필터를 이용한 방사선치료는 안전하고 효과적이며 국소제어율을 높이기 위해 수술과 방사선치료의 병합요법이 바람직하며 방사선 단독으로 치료할 때는 국소제어와 생존율을 향상시키기 위해 정교한 치료계획을 통해 방사선량을 증가시키고 다학제 치료를 고려해야 할 것이다.