• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1563-1570
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• 2017

In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of $epoxy/clay/B_4C$ and $epoxy/clay/B_4C/carbon$ fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of $epoxy/clay/B_4C$ instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.52-57
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• 2004

해체부지 선량평가 모델의 주요 핵종에 대한 key parameter를 분석하기 위하여 민감도 분석을 수행하였다. 본 연구에서 민감도 분석을 수행하기 위한 주요 가정 사항으로서 피폭시나리오는 가장 보수적인 resident farmer를 그리고 방사성핵종의 오염 정도는 0.037 Bq/g로 하였다. 분석결과, 감마 방출 핵종인 Cs-137과 Co-60의 경우에는 오염지역의 면적과 거주관련 변수(외부감마차폐인자와 실내 거주시간분율), C-14 핵종의 경우에는 환경변수와 불포화층의 수문학적 변수가, Sr-90 핵종의 경우에는 오염지역의 토양 밀도가 선량에 미치는 영향이 큰 parameter로 확인되었다.

• Archives of Pharmacal Research
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• 제28권11호
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• pp.1302-1310
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• 2005

Glucosylated polyethylenimine (GPEI) was synthesized as a tumor-targeting gene carrier through facilitative glucose metabolism by tumor glucose transporter. Particle sizes of GPEI/DNA complex increased in proportion to glucose content of GPEI, whereas surface charge of the complex was not dependent on glucosylation, partially due to inefficient shielding of the short hydrophilic group introduced. GPEI with higher glucosylation (36 mol-$\%$) had no cytotoxic effect on cells even at polymer concentrations higher than 200 $\mu$g/mL. Compared to unglucosylated PEl. glucosylation induced less than one-order decrease of transfection efficiency. Transfection of GPEI/DNA complex into tumor cells possibly occurred through specific interaction between glucose-related cell receptors and glucose moiety of GPEI. Gamma imaging technique revealed GPEI/DNA complex was distributed in liver. spleen. and tumors.

• Journal of electromagnetic engineering and science
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• 제1권1호
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• pp.67-72
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• 2001

In this paper, the plano-convex lens antenna fed by a single patch is studied for a microwave remote-traffic monitoring sensor with constraints of small size and low cost. Measurement of an AUT (Antenna Under Test) involves the considerations of a triangular groove for matched layer and metallic shielding effects. A formulation for extracting the parameters of a piano-convex lens antenna, based on geometrical optics, is introduced using Fermat`s principle of the equi-phased ray condition. Teflon ($\varepsilon_{{\gamma}}$/ =2.0) is chosen as a material of a plano-convex lens antenna for adjustment of aberrations on the lens surfaces automatically. A fabricated plano-convex lens shows 3-dB beamwidth of 7.5 degree and side-lobe level of -29 dB with an aperture distribution of the parabolic-squared taper on pedestal. This lens supports easier integration with the planar microwave circuits by using a microstrip single patch as a primary feeder of the lens antenna.feeder of the lens antenna.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2221-2229
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• 2022

In this research, for improving the measurement performance of Prompt Gamma-ray Neutron Activation Analysis (PGNAA) set-up, a new optimization method for set-up design was proposed and investigated. At first, the calculation method for Signal-to-Noise Ratio (SNR) was proposed. Since the SNR could be calculated and quantified accurately, the SNR was chosen as the evaluation parameter in the new optimization method. For discussing the feasibility of the SNR optimization method, two kinds of PGNAA set-ups were designed in the MCNP code, based on the SNR optimization method and the previous signal optimization method, respectively. Meanwhile, the single element spectra analysis method was proposed, and the analysis effect of single element spectra as well as element sensitivity were used for comparing the measurement performance. Since the simulation results showed the better measurement performance of set-up designed by SNR optimization method, the experimental set-ups were built for the further testing, finally demonstrating the feasibility of the SNR optimization method for PGNAA setup design.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2166-2171
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• 2023

In the present study, six silicone rubber doped by tellurium borate oxides were fabricated using the casting method. The densities of the fabricated silicon rubber-doped by tellurium borate oxides samples were measured using the Archimedes Method. Moreover, the linear attenuation coefficient of silicone rubber doped tellurium borate oxides samples was evaluated experimentally using the hyper pure germanium, and the recorded linear attenuation coefficient values were affirmed using the theoretical Phy-X program. The experimental measurements were performed using the narrow beam transmission method with radioactive isotopes Am-241, Cs-137, and Co-60 with energies of 59, 661, 1173, and 1332 keV. The linear attenuation coefficient values showed an enhancement by 4.73 times, 1.20 time, 1.17, time, and 1.17 time, respectively at gamma photon energies of 59, 661, 1173, and 1332 keV, when the TeO₂ concentration increased in the fabricated composites from 0 to 50 wt%. The enhancement of the linear attenuation coefficient values has a positive effect on the transmission rate values where the half-value thickness and transmission rate were decreased accompanied by an increase in the RPE.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3913-3923
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• 2023

Todays, medium energy resolution detectors are preferably used in radioisotope identification devices(RID) in nuclear and radioactive material categorization. However, there is still a need to develop or enhance « automated identifiers » for the useful RID algorithms. To decide whether any material is SNM or NORM, a key parameter is the better energy resolution of the detector. Although masking, shielding and gain shift/stabilization and other affecting parameters on site are also important for successful operations, the suitability of the RID algorithm is also a critical point to enhance the identification reliability while extracting the features from the spectral analysis. In this study, a RID algorithm based on Bayesian statistical method has been modified for medium energy resolution detectors and applied to the uranium gamma-ray spectra taken by a LaBr3:Ce detector. The present Bayesian RID algorithm covers up to 2000 keV energy range. It uses the peak centroids, the peak areas from the measured gamma-ray spectra. The extraction features are derived from the peak-based Bayesian classifiers to estimate a posterior probability for each isotope in the ANSI library. The program operations were tested under a MATLAB platform. The present peak based Bayesian RID algorithm was validated by using single isotopes(²⁴¹Am, ⁵⁷Co, ¹³⁷Cs, ⁵⁴Mn, ⁶⁰Co), and then applied to five standard nuclear materials(0.32-4.51% at.²³⁵U), as well as natural U- and Th-ores. The ID performance of the RID algorithm was quantified in terms of F-score for each isotope. The posterior probability is calculated to be 54.5-74.4% for ²³⁸U and 4.7-10.5% for ²³⁵U in EC-NRM171 uranium materials. For the case of the more complex gamma-ray spectra from CRMs, the total scoring (ST) method was preferred for its ID performance evaluation. It was shown that the present peak based Bayesian RID algorithm can be applied to identify ²³⁵U and ²³⁸U isotopes in LEU or natural U-Th samples if a medium energy resolution detector is was in the measurements.

• Radiation Oncology Journal
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• 제24권4호
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• pp.280-284
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• 2006

목 적: 원자력의학원에 설치되어 있는 MC50 사이클로트론에서 생성되는 중성자선의 의학적 이용을 위하여 생물학적 특성을 평가하고자 하였다. 대상 및 방법: 35 MeV 양성자를 15 mm 베릴륨 표적에 부딪혀서 생성된 중성자선에 대하여 물리적 방사선선량을 측정한 후 체외실험(in-vitro)을 하였다. EMT-6 세포주(cell line)를 이용하여 $0{\sim}5\;Gy$의 중성자선을 조사 후 생존분획(surviving fraction)을 구하였다. 또한 감마선의 효과를 피하기 위하여 납차폐를 한 후에 동일 조건에서 생존분획을 구하였다. 엑스선 실험에서는 0, 2, 5, 10, 15 Gy를 조사 후 생존분획을 측정하였다. 결 과: MC50의 중성자선은 조사야 $26{\times}26\;cm^2$, 전류 $10{\mu}A$, 깊이 2 cm에서 84%의 중성자와 16%의 감마선으로 구성되어 있었고, 총선량률은 9.25 cGy/min이었다. 엑스선을 이용하여 측정한 생존분획곡선은 선형이차함수모델 (linear quadratic model)을 적용하였을 때 ${\alpha}/{\beta}$비는 0.611 (${\alpha}=0.0204,\;{\beta}=0.0334,\;R^2=0.999$)이었다. 중성자선에 있어서 생존분획곡선은 저선량 영역에서 어깨영역(shoulder area)을 가지고 있었고, 모든 실험에서 선형이차함수모델에 잘 맞았다. ${\alpha}$의 평균값은 -0.315 (범위, $-0.254{\sim}-0.360$)였고, ${\beta}$값은 0.247 (범위, $0.220{\sim}0.262$)이었다. 납차폐를 하였을 때에도 생존분획곡선에서 어깨영역은 없어지지 않았다. 중성자선의 RBE (relative biological effectiveness) 값은 생존분획이 0.1일 때 $2.07{\sim}2.19$ 범위였고, 0.01일 때 $2.21{\sim}2.35$였다. 결 론: MC50에서 생성된 중성자선은 상당량의 감마선을 내포하고 있으며 이것이 생존분획곡선에서 어깨영역이 나타나는 데에 기여하였을 것이다. MC50의 중성자선의 RBE 값은 약 2.2였다.

• Journal of Radiation Protection and Research
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• 제39권1호
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• pp.21-29
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• 2014

삼축분광장치는 물질을 이루고 있는 자성 원소들의 거동, 즉 스핀 동역학을 측정하는데 적합한 장치로, 연구용 원자로 '하나로'에는 국내 유일의 냉중성자 삼축분광장치가 최근 설치되었다. 삼축분광장치는 중성자 빔을 제어하는 중성자광학 부품과 중성자 빔으로 인해 발생하는 방사선에 대한 차폐체로 이루어지며 이러한 부품은 수십 톤 중량의 기계구조물을 이룬다. 방사선 차폐는 중성자 빔 경로 이외의 방향으로 진행하는 중성자와 감마선을 효과적으로 막아 신호대 잡음비를 향상시키는 역할을 하며 구조물 내부의 방사화된 부품으로부터 발생하는 감마선을 차폐하여 장치 이용자의 피폭선량을 최소화한다. 그런데 설치된 냉중성자 삼축분광장치의 차폐체 중 전면부의 고하중으로 인해 장치 운영상 여러 가지 문제점이 발생, 전면 세그먼트 차폐체의 하중을 줄이는 구조개선이 불가피하였다. 이에 MCNPX 모의계산을 통해 냉중성자 삼축분광장치의 차폐체 최적화에 필요한 개선방향을 검토하였다. 상부 차폐체의 폴리에틸렌과 납의 추가 설치를 통해 전면 블록 차폐체 하중을 줄일 수 있는 최적 길이를 확인하였다. 그 결과, 전면 블록 차폐체의 높이 20%가 제거된 경우, 구조변경 전 대비 차폐체 상부에서 70% 수준의 감마선속이 나타남을 확인하였다. 하지만 높이를 줄일수록 전면 블록 차폐체의 하중을 줄일 수 있기 때문에, 차폐블록을 추가 제거하고 이에 대한 차폐능을 보상해 줄 방안으로 상부 납 차폐체의 위치 변화에 따른 중성자속과 감마선속을 예측해 보았다. 전면 블록 차폐체 높이의 35% 제거하고 상부 납 차폐체를 최하단부에서 10 cm에 설치한 경우, 전면 블록 차폐체 상부에서 감마선속이 각각 25%, 18% 증가하였다. 증가한 감마선속의 영향을 파악하기 위해 MCNPX 모의계산을 통해 공간의 감마선속 분포를 가시화하였다. 증가한 감마선속은 상부로 향하는 방향성을 띄며 이동하면서 소멸하여 검출기에 이르기 전에 낮아져 검출기와 실험자의 위치에 영향을 끼칠 수 없다고 판단하였다. 그래서 중성자속 및 감마선속과 고하중 문제를 동시에 해결할 수 있는 최적화 조건으로 차폐체 높이가 35% 제거되고 상부 납 차폐체가 10 cm 위치에 있는 경우를 선정하였다. 이 결과를 바탕으로 구조개선 작업을 실시하였으며 열형광선량계를 이용하여 콘크리트 차폐블록 외부에서 중성자와 감마선량을 측정하였다. 측정된 중성자 선량은 0.21 ${\mu}Svhr^{-1}$, 감마선량은 3.69 ${\mu}Svhr^{-1}$로 설계기준을 만족하였으며 피폭으로부터 실험자의 안전성을 확인하였다.

• 한국의료질향상학회지
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• 제20권1호
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• pp.60-73
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• 2014

Objectives: This study aims at decreasing spatial dose rate through work improvement whilst spatial dose rate is the cause of increasing personal exposure dose which occurs in the process of handling radioisotope. Methods: From February 2013 until July 2013, divided into "before" and "after" the improvement, spatial dose rate in laboratory of nuclear medicine was measured in gamma image room, PET/CT-1 image room, and PET/CT-2 image room as its locations. The measurement time was 08:00, 12:00 and 17:00, and SPSS 21.0 USA was opted for its statistical analysis. Result: The spatial dose rate at distribution worktable, injection table, the entrance to the distribution room, and radioisotope storage box, which had showed high spatial dose rate, decreased by more than 43.7% a monthly average. The distribution worktable, that had showed the highest spatial dose rate in PET/CT-1 image room, dropped the rate to 42.3% as of July. The injection table and distribution worktable in the PET/CT-2 image room also showed the decline of spatial dose rate to 89% and 64.4%, respectively. Conclusion: By improving distribution process and introducing proper radiation shielding material, we were able to drop the spatial dose rate substantially at distribution worktable, injection table, and nuclide storage box. However, taking into account of steadily increasing amount of radioisotope used, strengthening radiation related regulations, and safe utilization of radioisotope, the process of system improvement needs to be maintained through continuous monitoring.