• Journal of Radiation Protection and Research
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• 제37권4호
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• pp.197-201
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• 2012

경수로 사용후핵연료 중간저장시설의 부지면적을 산출하기 위하여 콘크리트 저장시설 개념모델의 연간선량을 계산하였다. 초기농축도 4.5 wt%, 연소도 45,000 MWd/MTU, 냉각기간 10년인 사용후핵연료를 대상으로 ORIGEN-ARP를 사용하여 선원항을 생산하였으며, MCNP 코드를 사용하여 저장시설에 대한 모델링 및 방사선차폐계산을 수행하였다. 연간선량은 저장시설의 용량별로 계산하였으며, 중앙집중식 저장시설의 경우, 반경 700 m 이상에서 10CFR72에서 권고하는 통제구역 경계에서의 연간선량 기준 0.25 mSv를 만족하였다.

• The Journal of Korean Physical Therapy
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• 제12권2호
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• pp.69-82
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• 2000

Physical therapists are exposured to radio-and microwave-frequency electromagnetic radiation by operating electrotherapy units. So there is few protection system in physical therapy room. Clinical pathology room and so on where various kins of electromagnetic instruments is used in hospital while protection failities like protection wall or protection glass is being used only in radiological room to reduce the damage of radiation. Acoording to Larsen's survey on female physical therapist in denmark. it was said that the percentage of congenital malfornation was $3.6\%$ and cadiac malformation made up $0.7\%$. It is likely that effect of electromagnetic fields on the result cannot be ruled out. Rita ouellet-Hellstron and Walter F. Steward insisted that the danger of abortion increase in the case of pregnant femeal physical therapist exposured to microwave diathermy. The intention of our study is arousing the necessity of microwave protection in P.T room and finding the proper method for physical therapist safe. The results of this study were as follows: 1. Each electrotherapy units are occurrenced the electromagnetic fields, and specially amply occurrenced in H.P,I.C.T 2 unit operating, M.W.D unit head on parallel, S.W.D unit head on parallel. all electrotherapy units are operating. 2. There were electric fields mount are consideration to species of electrotherapy units(p<.05). 3. There were magnetic fields mount are consideration to species of electrotherapy units(p<.05). 4. There were electric fields mount are consideration to distance of electrotherapy units(p<.05). 7. There were magnetic fields mount are consideration nut to distance of electrotherapy units(p>.05). 8. Before and after protection on magnetic fields mount are consideration to all distance(0m, 0.3m, 1m, 3m, 5m)(p<.05) 9. Before and after protection on electric fields mount are consideration to 0m, 1m, 3m distance(p<.05), and consideration not to 0.3m, 5m distance(p>.05) 10. After protection fellow the each electrotherapy units. distance, intencity to electromagnetic fields are reduced(p<.05).

• Journal of Radiation Protection and Research
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• 제39권4호
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• pp.176-181
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• 2014

The object of this paper is to evaluate the fission product inventories and radiological doses in a non-LOCA event, based on the U.S. NRC's regulatory methodologies recommended by the TID-14844 and the RG 1.195. For choosing a non-LOCA event, one fuel assembly was assumed to be melted by a channel blockage accident. The Hanul nuclear power reactor unit 6 and the CE $16{\times}16$ fuel assembly were selected as the computational models. The burnup cross section library for depletion calculations was produced using the TRITON module in the SCALE6.1 computer code system. Based on the recently licensed values for fuel enrichment and burnup, the source term calculation was performed using the ORIGEN-ARP module. The fission product inventories released into the environment were obtained with the assumptions of the TID-14844 and the RG 1.195. With two kinds of source terms, the radiological doses of public in normal environment reflecting realistic circumstances were evaluated by applying the average condition of meteorology, inhalation rate, and shielding factor. The statistical analysis was first carried out using consecutive three year-meteorological data measured at the Hanul site. The annual-averaged atmospheric dispersion factors were evaluated at the shortest representative distance of 1,000 m, where the residents are actually able to live from the reactor core, according to the methodology recommended by the RG 1.111. The Korean characteristic-inhalation rate and shielding factor of a building were considered for a series of dose calculations.

• 대한방사선기술학회지:방사선기술과학
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• 제38권3호
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• pp.237-244
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• 2015

핵의학 종사자는 PET/CT 업무 환경 중 방사성 의약품 취급 시 상당히 높은 피폭선량을 받는다고 알려져 있으며, 이를 최소화하기 위해 적절한 차폐기구의 사용이 요구된다. 이에 본 연구에서는 몬테카를로 기법을 기반으로 한 모의실험과 실측을 통해 18F-FDG 선원 취급 시 Apron 착용에 대한 차폐효과에 대해 분석하였다. 그 결과, 모의실험의 경우 선원의 취급 위치에 따라 인체 장기별 선량 분포가 각각 다른 양상을 나타냈고, Apron 납 두께별 선량 감소율은 선원과 장기와의 위치가 근접할수록, 선원과의 접촉 거리가 멀수록 낮은 경향을 나타냈다. 선량 측정 장비를 통한 실측의 경우, 측정 장비간 특성으로 인해 평균 공간 선량률 분포는 상이한 결과를 보였으나, 거리별 납 당량의 증가에 따라 지수함수분포로 공간 선량률이 감소되었다.

• Nuclear Engineering and Technology
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• 제56권9호
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• pp.3558-3565
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• 2024

The linear attenuation coefficients (LAC) of four soils (Black cotton (S1), Sandy (S2), Clay (S3), and Sandy (S4)) samples were measured at photon energies released from radioisotopes Co⁵⁷ (122 keV), Ba¹³³ (356 keV), ²²Na (511 and 1275 keV), Cs¹³⁷ (662 keV), Mn⁵⁴ (840 keV), and Co⁶⁰ (1330 keV) using a gamma spectrometer includes a NaI (Tl) scintillation detector. The experimental measurements were confirmed utilizing the Monte Carlo N-particle transport code. The linear attenuation coefficient values enhanced from 0.256 cm^-1 to 0.296 cm^-1 (at E_γ of 122 keV), from 0.126 cm^-1 to 0.142 cm^-1 (at E_γ of 662 keV), and from 0.0938 cm^-1 to 0.105 cm^-1 (at E_γ of 1275 keV), raising the (Fe + Mn) concentration from 0.912 wt% to 11.214 wt%, as well as raising the soil samples density from 1.62 g/cm³ to 1.79 g/cm³. The study also shows an enhancement in the half value thickness, transmission factor, radiation protection efficiency and lead's equivalent thickness due to the enrichment of Fe + Mn concentrations within the studied soils. The results show that the Black cotton soil exhibits better shielding properties for γ-ray than the other soils.

• Journal of Radiation Protection and Research
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• 제26권2호
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• pp.67-71
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• 2001

극저준위 방사능측정시스템의 백그라운드에 영향을 주는 중성자를 차폐하기 위한 차폐체를 설계하였다. 중성자 차폐방법은 고 밀도 폴리에틸렌을 이용하여 고속중성자를 감속한 후 $B_4C$를 이용하여 감속된 열중성자를 흡수하는 방법을 이용하였다. 몬테카를로 모사방법인 MCNP4B 코드를 이용하여 계산한 결과 고 밀도 폴리에틸렌의 두께가 10 cm 일 때 열중성자속이 최대가 되는 것으로 나타났으며 감속된 중성자의 흡수는 용제에 자연상태의 $B_4C$ 분말을 30 w% 섞을 경우 2 mm의 두께에서 94%의 중성자 흡수가 일어나는 것으로 나타났다. 또한 몬테카를로 모사를 통한 계산결과의 타당성 여부를 조사하기 위하여 중성자 차폐실험 장치를 제작하여 실험 결과와 비교하였으며, 비교 결과 실험값과 일치하는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제56권7호
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• pp.2740-2747
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• 2024

The sintering process acquired ferromagnetic copper ferrite ceramic material with a small concentration of Ni ion at 1100 ℃ for 1 h. Previously, copper ferrite with Ni proportions powder was acquired by the wet chemical process according to the relation CuFe_2-xNi_xO₄ where x takes values 0.0, 0.015, 0.03, 0.04, and 0.05. The role of Ni ion in the copper ferrite structure was investigated by X-ray analysis, Scanning electron microscope, EDX analysis, and density measurements. The gamma-ray shielding properties for the fabricated CuFeNiO ceramics samples were evaluated using the Monte Carlo simulation method. The obtained results show an enhancement in the linear attenuation coefficient for the fabricated ceramics with increasing the insertions of Ni ions within the fabricated samples, where increasing the Ni ions concentration between 0 and 1.19 wt% increases the linear attenuation by between 1.581 and 1.771 cm^-1 (at 0.103 MeV), 0.304-0.338 cm^-1 (at 0.662 MeV), and 0.160-0.178 cm^-1 (at 2.506 MeV), respectively. Simultaneously, the radiation protection efficiency for a 1 cm thickness of the fabricated samples increased between 14.8 and 16.3% with increasing the Ni ions between 0 and 1.19 wt%. Although the Ni doping concentration does not exceed 1.5 wt% of the total composition of the fabricated ceramics, the shielding capacity of the fabricated ceramics was enhanced by more than 11%, along the studied energy interval. Therefore, the fabricated samples can be used in gamma-ray shielding applications.

• 방사선산업학회지
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• 제18권1호
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• pp.23-33
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• 2024

This study was conducted to analyze the characteristics of three high-exposure tasks performed by radiation workers in Korean pressurized water reactors (PWRs) and to identify factors that reduce their exposure during work. Three high-exposure tasks were selected based on a previous study. In this previous study, nozzle dam installation and removal, eddy current testing, and manway opening and closing were determined as high-exposure tasks through normalization (radiation dose per unit time). Based on the analysis of the characteristics of the high-exposure tasks in this study, the high-exposure tasks were steam generator-related tasks performed inside and outside the water chamber. This study analyzed the reduction factors for high-exposure tasks and suggested improvements in terms of time, distance, and shielding. The use of the characteristics of high-exposure tasks and their dose reduction factors enables Korean PWRs to optimize radiation protection for workers who receive relatively high doses.

• 한국방사선학회논문지
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• 제5권3호
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• pp.155-159
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• 2011

이 연구의 목적은 방사선 발생 장치에 의한 환자나 작업 종사자들의 피폭과 사용시설에 대한 방어 상태를 조사하는데 있다. 수도권 대학병원의 엑스선 발생장치들을 대상으로 관전압 80 kVp, 관전류 200 mA, 1 sec의 최대 조사조건하에서 제어실출입문, 제어실감시창, 촬영실출입문, 인접주위 등에서 측정하였다. 주당누설선량은 제어실 출입문에서 0.11 mR/week, 제어실 감시창에서 0.15 mR/week, 촬영실 출입문에서 0.12 mR/week, 인접 주위에서 0.06 mR/week로 측정되었다. 그리고 주당평균누설선량은 0.11 mR/week 이었다. 구해진 주당평균누설선량은 기준치 100 mR/week 이하로 나타났으나 누설선량은 주기적인 측정으로 관리가 필요할 것으로 생각된다.

• 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.