• Journal of Welding and Joining
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• 제26권6호
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• pp.42-47
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• 2008

TIG welding enables to produce high quality weldment. However it has some problems such as shallow penetration and large distortion due to low penetration aspect ratio after welding. In order to overcome those problems, there are many ongoing studies on A-TIG welding, which use active flux. In this study, the effect of arc length and shield gas on penetration aspect ratio with melt-run welding on STS 304 6t, on which active flux was spreaded, was investigated. Arc length was changed from 1mm to 3mm, and aspect ratio became higher as arc length was decreased in this range. 100% Ar gas, Ar-$H_2$ mixed gas, Ar-He mixed gas, and 100% He gas were used as shield gas in this study. When Ar-$H_2$ mixed gas, Ar-He mixed gas, and 100% He gas were applied, penetration and melting efficiency were both increased as compared with 100% Ar gas. Aspect ratio was the highest with Ar-2.5% $H_2$ mixed gas.

• 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^-.

• 핵의학기술
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• 제14권2호
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• pp.65-76
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• 2010

1994년 PET의 국내 도입 이후, 현재까지 양적으로나 질적으로 많은 발전이 있었다. 하지만 이와 함께 방사성의약품의 사용량 또한 급증하면서 검사에 있어서 가장 중요한 역할을 하는 방사선사의 개인피폭선량이 높아지는 요인으로 작용했던 것이 사실이다. 식품의약품안전청의 피폭선량관리센터에서 발표한 자료에 따르면 2008년도 방사선작업종사자의 전체 평균 피폭선량은 0.67 mSv였고, 방사선사 전체 피폭선량은 1.33 mSv로 해마다 감소하는 것으로 나타났다. 설문결과를 살펴보면 PET 검사 담당자의 평균피폭선량은 1.69 mSv였고, 1.0 mSv를 초과하는 구간에 75.3%의 방사선사가 포함되어 있었다. 이는 고 노출구간에 속한 방사선사의 비율이 높다는 것을 의미하므로, 피폭저감을 위한 노력이 요구된다. 본 연구에서는 설문조사를 통하여 PET 검사 프러시저별 차폐기구의 활용에 따른 방사선 피폭 정도를 TLD 수치를 이용하여 분석하고, 실험을 통하여 각 차폐기구의 차폐율을 측정함으로써, 그 효용성을 입증하고 적합한 차폐방법을 강구하고자 하였다. 방사선 피폭의 위험에 대해서 어느 누구보다 잘 인지하고 있는 방사선사임에도 불구하고 안이하게 생각하는 경향이 있었다. 설문결과를 살펴보면 방사선 피폭의 위험성에 대한 인식도와 피폭선량과는 크게 관련이 없었으며, 차폐기구의 활용도에 따라서는 피폭선량의 차이가 확연하게 나타났다. 프러시저 중 피폭선량에 가장 많은 영향을 미치는 단계는 방사성의약품의 투여였으며, 투여시 차폐방법에 따라 이동시 차폐방법도 달라졌다. 투여 시 차폐기구 사용현황을 보면 Both shield는 58.5%, L-Block은 20%, Syringe shield는 9%, No shield는 12.3%를 차지하였다. TLD 수치에 따른 투여 시 차폐방법은 수치가 낮을수록 Both shield와 L-block을 많이 사용하였으며, 수치가 높을수록 Syringe shield와 차폐를 시행하지 않는 경우가 많았다. 실험결과, 가장 이상적인 차폐방법은 분배 시엔 L-block을 사용하고, 이동시엔 Syringe shield carrier를 사용하며, 투여 시엔 L-block과 Syringe shield를 함께 사용하는 것이다. 환자 포지셔닝 시 Apron의 차폐율은 평균 16.4%로 차폐효과가 있다. PET 검사를 시행함에 있어서 강한 실천의지를 가지고 프러시저별로 차폐기구를 적극 활용한다면 점증하는 방사선사의 피폭 수준을 크게 감소시킬 수 있을 것으로 판단된다.

• Journal of Advanced Marine Engineering and Technology
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• 제33권7호
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• pp.1017-1025
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• 2009

This study intends to study about the blade performance loss occurred due to the variation in the shape of airfoil from the attachment/non-attachment of blade erosion shield for hovercraft. This study model has used NACA 4412, has designed NACA 4412 by using Auto CAD and designed the shape that has attached an erosion shield to this model according to the thickness and length. By using these models, we have generated a grid by using GAMBIT and calculated the lift coefficient (Cl) and drag coefficient (Cd) by using the FLUENT code for flow analysis. Through this, we have calculated and compared the lift-to-drag ratio that is an indicator of airfoil performance according to the shape and attachment/non-attachment of erosion shield.

• 터널과지하공간
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• 제21권6호
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• pp.427-438
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• 2011

세그먼트 라이닝은 쉴드터널에서 공사 중의 안정성을 확보하고 영구적인 터널 라이닝으로 사용되는 중요한 구조체이다. 더욱이 세그먼트 라이닝은 쉴드터널의 공사비에서 가장 큰 비중을 차지하기 때문에, 세그먼트의 경제성 향상을 위한 기술적인 개선 노력들이 이루어지고 있다. 따라서 본 연구에서는 경제적인 세그먼트 라이닝의 시공을 위한 고성능 세그먼트의 최신 개발 동향을 조사 및 분석하여 세그먼트의 기술개발 방향을 제시하고자 하였다. 또한 설계단계에서 세그먼트의 주요 설계사항들을 개략적으로 추정하는데 활용하기 위하여, 전 세계 2,100여개 세그먼트 자료들을 조사하고 이를 기반으로 세그먼트 라이닝 외경, 세그먼트 주요 형상치수 및 세그먼트 재질들에 대한 통계분석을 실시하였다.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3855-3863
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• 2022

An evaluation of the radiation shielding performance of high-Z-particle-loaded polylactic acid (PLA) composite materials was pursued. Specimens were produced via fused deposition modeling (FDM) using copper-PLA, steel-PLA, and BaSO₄-PLA composite filaments containing 82.7, 75.2, and 44.6 wt% particulate phase contents, respectively, and were tested under broad-band flash x-ray conditions at the Sandia National Laboratories HERMES III facility. The experimental results for the mass attenuation coefficients of the composites were found to be in good agreement with GEANT4 simulations carried out using the same exposure conditions and an atomistic mixture as a model for the composite materials. Further simulation studies, focusing on the Cu-PLA composite system, were used to explore a shield design parameter space (in this case, defined by Cu-particle loading and shield areal density) to assess performance under both high-energy photon and electron fluxes over an incident energy range of 0.5-15 MeV. Based on these results, a method is proposed that can assist in the visualization and isolation of shield parameter coordinate sets that optimize performance under targeted radiation characteristics (type, energy). For electron flux shielding, an empirical relationship was found between areal density (AD), electron energy (E), composition and performance. In cases where ${\frac{E}{AD}}{\geq}2MeV{\bullet}cm{\bullet}g^{-1}$, a shield composed of >85 wt% Cu results in optimal performance. In contrast, a shield composed of <10 wt% Cu is anticipated to perform best against electron irradiation when ${\frac{E}{AD}}<2MeV{\bullet}cm{\bullet}g^{-1}$.

• Journal of Welding and Joining
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• 제31권6호
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• pp.90-95
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• 2013

Pipe inside clad welding is mainly used to the flow pipe of sub-sea or chemical plant. For the inside clad welding to the medium pipe with the diameter of about 12", TIG welding is frequently applied with filler metal. In this case, the clad welding has the very broad weld area over $10m^2$. And, the non-destructive test (NDT) such as ultrasonic test (UT) or radiographic testing (RT) should be conducted on the broad weld area, and it costs very high due to the time-consuming work. Therefore, the present study investigated the variation of arc voltage to develop the in-line quality monitoring system for the pipe inside TIG cladding. The 4 experimental parameters (current, arc length, wire feed position, and shield gas flow rate) varied to observe the change of arc voltage and to establish the model for the monitoring. The arc voltage was decreased when the wire was fed to the backward eccentric position(over 2mm), and the shield gas flow rate was insufficient under 10L/min. In the case of the backward eccentric position over 2mm, the bead appearance was not good and the dilution ratio was increased due to deep penetration. When the shield gas flow rate was lower than 10L/min, the bead surface was oxidized.

• 한국융합학회논문지
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• 제8권2호
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• pp.113-120
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• 2017

본 실험에서는 전산화단층영상장비에서 패각을 이용하여 제작한 방사선 융합차폐체의 표면 방사선 감소율과 방사선 인공물 영상을 평가하고자 하였다. 방사선 융합차폐체는 실리콘, 패각, 바륨분말을 이용하여 직경 50 mm, 두께 3.5 mm의 원형 차폐체 5종 (실리콘 차폐체, 바륨 차폐체, 실리콘과 패각 혼합 차폐체, 실리콘과 바륨 혼합 차폐체, 실리콘과 패각 그리고 바륨 혼합 차폐체)을 제작하였다. 방사선발생과 획득은 4 다중채널 전산화단층영상장비를 이용하였다. 그 결과 실리콘과 패각 혼합 차폐체가 영상의 인공물 발생 없이 5.3%의 표면 방사선 감소효과가 있었다. 향후 다양한 형태를 만들 수 있는 실리콘의 장점과 패각의 재활용으로 인한 친환경적인 소재로 방사선 융합차폐체 제작에 도움을 줄 수 있으리라 기대한다.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.130-141
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• 2020

Background: Concrete activation in cyclotron vaults is a major concern associated with their decommissioning because a considerable amount of activated concrete is generated by secondary neutrons during the operation of cyclotrons. Reducing the amount of activated concrete is important because of the high cost associated with radioactive waste management. This study aims to investigate the capability of the neutron absorbing materials to reduce concrete activation. Materials and Methods: The Particle and Heavy Ion Transport code System (PHITS) code was used to simulate a cyclotron target and room. The dimensions of the room were 457 cm (length), 470 cm (width), and 320 cm (height). Gd₂O₃, B₄C, polyethylene (PE), and borated (5 wt% ^natB) PE with thicknesses of 5, 10, and 15 cm and their different combinations were selected as neutron absorbing materials. They were placed on the concrete walls to determine their effects on thermal neutrons. Thin B₄C and Gd₂O₃ were placed between the concrete wall and additional PE shield separately to decrease the required thickness of the additional shield, and the thermal neutron flux at certain depths inside the concrete was calculated for each condition. Subsequently, the optimum combination was determined with respect to radioactive waste reduction, price, and availability, and the total reduced radioactive concrete waste was estimated. Results and Discussion: In the specific conditions considered in this study, the front wall with respect to the proton beam contained radioactive waste with a depth of up to 64 cm without any additional shield. A single layer of additional shield was inefficient because a thick shield was required. Two-layer combinations comprising 0.1- or 0.4-cm-thick B₄C or Gd₂O₃ behind 10 cm-thick PE were studied to verify whether the appropriate thickness of the additional shield could be maintained. The number of transmitted thermal neutrons reduced to 30% in case of 0.1 cm-thick Gd₂O₃+10 cm-thick PE or 0.1 cm-thick B₄C+10 cm-thick PE. Thus, the thickness of the radioactive waste in the front wall was reduced from 64 to 48 cm. Conclusion: Based on price and availability, the combination of the 10 cm-thick PE+0.1 cmthick B₄C was reasonable and could effectively reduce the number of thermal neutrons. The amount of radioactive concrete waste was reduced by factor of two when considering whole concrete walls of the PET cyclotron vault.

• Journal of Welding and Joining
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• 제20권1호
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• pp.76-82
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• 2002

In these days, many advanced nations have enforced import restrictions against things emitting electromagnetic wave which has report that it is so harmful. In general, electromagnetic wave is composed of electric wave and magnetic wave. The reflection of electromagnetic wave is mainly reflected by conductive materials and the magnetism loss is generated by magnetic ferrite. The magnetism loss of ferrite is separated by eddy current loss, residual magnetism loss and hysteresis loss. Thermal sprayed coating is intended to manufacture because of simple processes and high efficient electromagnetic wave shielding. The high efficient thermal sprayed coatings were made from the magnetic ferrite materials that characterizes absorption of electromagnetic wave, and the electric conductive materials that characterize emitting of electromagnetic wave. This study was manufactured thermal sprayed coatings to improve absorption-efficiency, and measured the electromagnetic wave shielding efficiency. As the experimental results, high electromagnetic wave shield efficiency was obtained at wave frequency 2GHz to thermal sprayed ferrite coatings manufactured by size distribution range of spray powders, $38~88\mu\textrm{m}$.