• Nuclear Engineering and Technology
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• 제20권1호
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• pp.65-70
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• 1988

PWR사용 후 핵연료 집합체 4개를 장전한 수 있는 납/Resin차폐체형 수송용기에 대한 방사선 차폐해석을 수행하였다. 이때 차폐효과를 유지하면서도 전체중량이 최소화되도록 차폐재를 선택하였다. 방사선윈은 ORIGEN 전산코드로 계산하여 얻었으며, 사용후 핵연료의 연소도를 38,000 MWD/MTU 그리고 냉각기간을 3년으로 가정하였다. 수송용기의 외부 표면에서 1m거리에서 나타나는 감마선 그리고 중성자의 선량율은 ANISN전산코드로 계산하여 얻었다. 계산된 총방사선 선량율은 정상 및 가상 사고조건하에서도 국내 법규에 규정된 기준치 이내에서 만족하는 것으로 나타났다.

• 한국의학물리학회지:의학물리
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• 제29권1호
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• pp.42-46
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• 2018

The purpose of this study was to perform a survey of the radiation shielding design goals (P) and workload (W) based on the radiation safety reports concerned with structural shielding design for the IMRT treatment technique in Tomotherapy vaults. The values of the P and W factors as well as of a verified concrete thickness of the ceiling, bottom, sidewalls (sidewall-1 and sidewall-2), and door have been obtained from radiation safety reports for a total of 16 out of 20 vaults. The recommended and most widely used report for P values was the NCRP No. 151 report, which stated that the P factor in controlled and uncontrolled areas was 0.1 and 0.02 mSv/week, respectively. The range of the W factor was 600~14,720 Gy/week. The absorbed dose delivered per patient was 2~3 Gy. The maximum number of patients treated per day was 10~70. The quality assurance (QA) dose was 100~1,000 Gy/week. Fifteen values of the IMRT factor (F) were mostly used but a maximum of 20 values was also used. The concrete thickness for primary structures including the ceiling, bottom, sidewalls, and door was sufficient for radiation shielding. The P and W factors affect the calculation of the structural shielding design, and several parameters, such as the absorbed dose, patients, QA dose, days and F factor can be varied according to the type of shielding structure. To ensure the safety of the radiation shielding, it is necessary to use the NCRP No. 151 report for the standard recommendation values.

• 한국방사선학회논문지
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• 제15권6호
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• pp.813-819
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• 2021

본 연구에서는 방사성 불소의 인체 내 주입 시 방사선 방호목적으로 사용되는 L-블럭형 방호장비의 차폐율과 주변공간의 선량분포를 몬테칼로 방법을 이용해 계산하였다. L-블럭형 차폐장치의 몸체 및 윈도우 부위의 차폐율은 99.99 %였다. 1 m거리에서 계산한 선량분포는 XZ평면의 135°, 45°, 225°, 315°, 180°에서 상대적으로 높게 나타났고, 0°, 90°, 270°에서는 매우 낮게 계산되었다. YZ평면에서는 135°, 180°, 225°에서 상대적으로 높게 나타났고, 나머지 각도에서는 매우 낮게 계산되었다. AZ와 BZ 평면에서도 YZ평면과 유사한 결과를 나타냈다. 또한 선원의 수평방향과 선원의 상방 45°방향의 선량분포를 통해 225°~315°범위에서 차폐율이 가장 우수함을 확인하였다. 이와 같은 결과가 방사선 작업 종사자들의 방사선 방호에 필요한 기초자료로 활용되기를 기대한다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1519-1526
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• 2023

For the first time Aluminium-BariumeZinc oxide nanocomposite (ZABONC) was synthesized by solution combustion method where calcination was carried out at low temperatures (600℃) to study the electromagnetic (EM) (X/γ) radiation shielding properties. Further for characterization purpose standard techniques like PXRD, SEM, UV-VISIBLE, FTIR were used to find phase purity, functional groups, surface morphology, and to do structural analysis and energy band gap determination. The PXRD pattern shows (hkl) planes corresponding to spinel cubic phase of ZnAl₂O4, cubic Ba(NO₃)₂, α and γ phase of Al₂O₃ which clearly confirms the formation of complex nano composite. From SEM histogram mean size of nano particles was calculated and is in the order of 17 nm. Wood and Tauc's relation direct energy band gap calculation gives energy gap of 2.9 eV. In addition, EM (X/γ) shielding properties were measured and compared with the theoretical ones using standard procedures (NaI (Tl) detector and multi channel analyzer MCA). For energy above 356 keV the measured shielding parameters agree well with the theory, while below this value slight deviation is observed, due to the influence of atomic/crystallite size of the ZABONC. Hence synthesized ZABONC can be used as a shielding material in EM (X/γ) radiation shielding.

• 대한전자공학회논문지TC
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• 제47권5호
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• pp.60-68
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• 2010

통신서비스에 장애를 유발하는 전력선에 의한 전자유도 현상에 대한 방호를 위하여는 유도전압을 평가하여야 하고 상응한 대책을 수행하여야 한다. 유도전압을 평가하는 방식은 ITU 규격과 일본 유도자료로부터 국내에 도입되어 법률 고시화되어 있는데 이것으로 수용되지 못하는 유도 커플링상의 제원 요소들이 있다. 본 논문에서는 계산 수행 적용이 곤란한 범위를 포괄할 수 있도록 좀더 일반화된 고전적 유도 및 전자파 원론 해석 근간의 전자계 형성에 의한 소스와 관측점의 유도전압 산출 방식에 대한 기술을 분석하여 제시하였다.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2001년도 하계학술대회 논문집
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• pp.609-612
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• 2001

To investigate the magnetic field distribution of power line, we used amorphous wire sensor. And we discuss extremely low frequency magnetic field distribution dependent upon arrangement of power line and shielding pipe made from iron or alumimum materials by both measurement and FEM(Finite Element Method) analysis. Appling current of single phase 60 [Hz] 15 [A] is supplied to copper wire coated enamel resign. As the results, we confirmed that linear characteristics of amorphous wire sensor is very excellent and measurement value agrees with FEM calculation. Magnetic field distribution due to shielding materials is changed by permeability and conductivity.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.847-852
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• 1995

A shielding analysis for KSC-7, the shipping cask for transporting the 7 PWR spent fuel assemblies, has been carried out. Radiation source term has been calculated on spent fuel with burnup of 50,000 MWD/MTU and 1.5 years cooling time by ORIGEN2 code. The shielding calculation for the cask has been made by using MCNP4A code with continuous cross section data library from ENDF/B-V. As a result of neutron dose rate analysis, another shielding calculational model on spent fuel shipping cask was provided which is using the Monte Carlo method.

• 대한방사선기술학회지:방사선기술과학
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• 제40권2호
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• pp.281-287
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• 2017

본 연구는 방사선 차폐 시 주로 사용되고 있는 콘크리트를 대상으로 차폐 두께를 계산한 연구로서 의료용 선형가속기를 차폐하기 위해 구성되는 벽에 대한 연구이다. 선형가속기에서 발생하는 광자선 에너지 10 MV를 대상으로 MCNPX(Ver.2.5.0)를 이용하여 적절한 차폐 두께를 계산하고자 하였다. 그 결과, 광자선 차폐를 위한 십가층은 순수 콘크리트의 경우 50~100 cm, Boron+polyethylene 첨가 시 80~100 cm에서 형성되었다. 중성자 차폐는 순수 콘크리트의 경우 100~140 cm, Boron+polyethylene 첨가 시 90~100 cm으로 계산되었다. 이를 바탕으로 분석하면, 콘크리트 재질은 Steel 계열을 사용하고 콘크리트에 Boron+polyethylene을 첨가하여 구성하는 것이 가장 효율적인 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3854-3859
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• 2023

Background: This study aims to develop an evaluator that can quickly and accurately evaluate the shielding of low-energy industrial radiation generators. Methods: We used PyQt to develop a graphical user interface (GUI)-based program and employed the calculation methodology reported in the National Council on Radiation Protection and Measurements (NCRP)-49 for shielding calculations. We gathered the necessary factors for shielding evaluation using two libraries designed for Python, pandas and NumPy, and processed them into a database. We verified the effectiveness of the proposed program by comparing the results with those from safety reports of six domestic facilities. Results: After verifying the effectiveness of the program using the NCRP-49 example, we obtained an average error rate of 1.73%. When comparing the facility safety report and results obtained using the program, we found that the error rate was between 1.09% and 6.51%. However, facilities that did not use a defined shielding methodology were underestimated by 31.82% compared with the program (the final barrier thickness satisfied the shielding standard). Conclusion: The developed program provides a fast and accurate shielding evaluation that can assist personnel that work in radiation generator facilities and government officials in reviewing safety.

• 대한전기학회논문지:전기물성ㆍ응용부문C
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• 제51권1호
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• pp.5-14
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• 2002

In this paper, we analyze inductive interference in conductive material around 345 kV power transmission line, and evaluate the effects of mitigation wires. Finite element method (FEM) is used to numerically compute induced eddy currents as well as magnetic fields around powder transmission lines. In the analysis model, geometries and electrical properties of various elements such as power transmission line, buried pipe lines, overhead ground wire, and conducting earth are taken into accounts. The calculation shows that mitigation wire reduces fairly good amount of eddy currents in buried pipe line. To find the optimum magnetic field shielding location of mitigation wire, we applied evolution strategy algorithm, a kind of stochastic approach, to the analysis model. Finally, it was shown that we can find more effective shielding effects with optimum location of one mitigation wire than with arbitrary location of multi-mitigation wires around the buried pipe lines.