• The Korean Journal of Nuclear Medicine Technology
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• v.20 no.2
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• pp.27-31
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• 2016

Purpose $^{99m}Tc-DMSA$ renal scan is a test for the comparison of the function by imaging the parenchyma of the kidneys by the cortex of a kidney and by computing the intake ratio of radiation by the left and right kidney. Since the distance between the kidneys and the bladder is not far given the bodily structure of an infant, the bladder is included in the examination domain. Research was carried out with the presumption that counts of bladder would impart an influence on the kidneys at the time of this renal scan. In consideration of the special feature that only a trace amount of a RI is injected in a pediatric examination, research on the method of injection was also carried out concurrently. Materials and Methods With 34 infants aged between 1 month to 12 months for whom a $^{99m}Tc-DMSA$ renal scan was implemented on the subjects, a Post IMAGE was acquired in accordance with the test time after having injected the same quantity of DMSA of 0.5mCi. Then, after having acquired an additional image by shielding the bladder by using a circular lead plate for comparison purposes, a comparison was made by illustrating the percentile of (Lt. Kidney counts + Rt. Kidney counts)/ Total counts, by drawing the same sized ROI (length of 55.2mm X width of 70.0mm). In addition, in the format of a 3-way stopcock, a Heparin cap and direct injection into the patient were performed in accordance with RI injection methods. The differences in the count changes in accordance with each of the methods were compared by injecting an additional 2cc of saline into the 3-way stopcock and Heparin cap. Results The image prior to shielding of the bladder displayed a kidney intake rate with a deviation of $70.9{\pm}3.18%$ while the image after the shielding of the bladder displayed a kidney intake rate with a deviation of $79.4{\pm}5.19%$, thereby showing approximately 6.5~8.5% of difference. In terms of the injection method, the method that used the 3-way form, a deviation of $68.9{\pm}2.80%$ prior to the shielding and a deviation of $78.1{\pm}5.14%$ after the shielding were displayed. In the method of using a Heparin cap, a deviation of $71.3{\pm}5.14%$ prior to the shielding and a deviation of $79.8{\pm}3.26%$ after the shielding were displayed. Lastly, in the method of direct injection into the patient, a deviation of $75.1{\pm}4.30%$ prior to the shielding and a deviation of $82.1{\pm}2.35%$ after the shielding were displayed, thereby illustrating differences in the kidney intake rates in the order of direct injection, a Heparin cap and the 3-way methods. Conclusion Since a substantially minute quantity of radiopharmaceuticals is injected for infants in comparison to adults, the cases of having shielded the bladder by removing radiation of the bladder displayed kidney intake rates that are improved from those of the cases of not having shielded the bladder. Although there are difficulties in securing blood vessels, it is deemed that the method of direct injection would be more helpful in acquisition of better images since it displays improved kidney intake rate in comparison to other methods.

• Aerospace Engineering and Technology
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• v.8 no.1
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• pp.17-25
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• 2009

The precise calculation of gas absorption coefficient in the radiative transfer equation is very important to the prediction of radiative heat transfer induced from liquid engine plume in view of base insulation design. For this purpose, the WNB model for gas absorption coefficient is described with the selection of important parameters and then the calculated results are compared with those of SNB model for validation. Total emissivity, narrow band averaged intensity and total intensity are calculated and compared to the results of SNB model. As results, the total emissivity and the total intensity are well matched within 3.1% and roughly 5 % error, respectively. Moreover, the gas modeling database is constructed with estimation of the combustion gas composition of $CO_2$ and $H_2O$ for liquid engine plume.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.12 no.2
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• pp.151-159
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• 1992

In close-range photogrammetry, to employ non-metric camera especially for the purpose of precise measurement, systematic errors must, first of all, be corrected as they have a great influence on accuracies of results. For it, fiducial marks was built in non-metric camera and the factors such as PPS, PPA, EFL, CFL, and radial lens distortion coefficients for each quadrant were calibrated through collimator test. Also, the coefficients of both radial and tangential lens distortion were calibrated from analytical plumb line method and therefore main systematic errors could be effectively corrected. Using the calibrated non-metric camera, close-range photogrammetry could be successfully accomplished and accuracies could be improved sharply.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.39 no.6
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• pp.559-566
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• 2011

This paper presents the flow passage design for a window cooling device, which have a conical poppet valve and an emissive orifice. Computational flow analysis and experiment are conducted according to the poppet strokes. The results show satisfactory flow characteristics that pressure is reduced enough to endure material strength and the flow does not choked inside window. The correction factor of discharge coefficients is found between 2-dimensional analysis and experiments, which is applied to control coolant flow rates of the window cooling device.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.78-82
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• 2003

For the decomposition of laundry wastewater containing Fe-EDTA produced from the steam generators in nuclear power plants, Supercritical Water Oxidation (SCWO) Process, Photocatalytic Oxidation (PO) Process, and Dielectric Barrier Discharge (DBD) Atmospheric Pressure Plasma Process were evaluated. Even though EDTA was converted over 99.98 % by the SCWO process, it was estimated that the countermeasure against corrosion of the equipment should be reinforced for the process stability. It was considered that the PO process is not appropriate for the decomposition of high concentrated laundry wastewater since the conversion ratio of EDTA was around 10 %. Finally, High efficiency of the decomposition of organic matter (methylene blue) was obtained using DBD process even low energy was supplied. However there is still room for the evaluation of EDTA decomposition in order that the DBD process should be applied for the field samples.

• Proceedings of the Korea Water Resources Association Conference
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• 2005.05b
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• pp.250-254
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• 2005

국내의 상수원수 확보는 대부분을 표류수에 의존하고 있으나, 표류수의 경우 수질오염의 증가와 돌발 수질 오염 사고에 대한 대응 등의 취약점을 가지고 있다. 이러한 문제점을 해결하기 위해 근본적으로 깨끗한 상수원수를 확보하기 다양한 방법이 모색되어지고 있다. 수량적으로 안정적이고, 수질적으로 안전한 상수원수 취득 방법으로 강변여과수, 지하댐, 인공함양기법 등이 실질적으로 계획되어 시행되어지고 있다. 특히 강변 충적층의 자연정화 기능을 이용한 강변여과수 개발은 지하수 개발과 달리 수량적으로 안정적이고, 수질적으로 안전한 강변여과수 개발 방안이 적극적으로 진행되고 있다. 낙동강 하류 지역인 함안군, 창원시, 김해시 등은 대부분 하천 표류수에 의존하였으나, 유역내 충적층 발달 지역이 분포해 있고, 하상경사, 하상계수 등의 하천공학적 측면에서 강변여과수 개발에 유리한 입지조건을 가지고 있어 강변여과수 개발이 진행되고 있다. 현재 창원시 대산면 일대에서 국내최초로 방사형집수정을 이용한 강변여과수 개발이 진행되고 있으며, 현재 방사형 취수정 1기가 시공 완료되어 시험 가동 중에 있다. 본 연구에서는 창원시 대산면 일대에서 진행되고 있는 방사형 집수정 설치에 따른 양수시험을 실시하여 양수량에 따른 수위하강 겋항 등을 분석하여 적정 산출량을 결정하였고, 계획단계에서 적정 산출량 예상시 사용한 경험식(Petrovic, Milojevic 경험식)의 적합성 여부에 중점을 두어 진행 되었다. 연구대상 지역인 창원시 대산면 일대는 지하수위가 하천수위보다 높은 이득하천의 형태로 건기시 하천특성을 뚜렷하며, 양수실험을 위한 대용량 양수펌프 설치, 유량검증을 위한 대형 웨어 설치, 수위변화 측정을 위한 디지털 수위계 등을 설치하여 실험을 수행하였다. 단계/장기양수시험을 통하여 양수량-수위하강 경향을 분석하여 방사형 집수정 1기의 적정 양수량은 약 $16,000m^3/day$로 예상하였으며, 계획 시 사용한 경험식(Milojevic)으로 산정된 산출예상량과 유사한 특성을 나타내었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.3
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• pp.213-229
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• 2005

Nuclides in radioactive wastes are assumed to be transported in the geosphere by groundwater and probably discharged into the biosphere. Quantitative evaluation of doses to human beings due to nuclide transport in the geosphere and through the various pathways in the biosphere is the final step of safety assessment of the radioactive waste repository. To calculate the flux to dose conversion factors (DCFs) for nuclides appearing at GBIs with their decay chains, a template ACBIO which is an AMBER case file based on mathematical model for the mass transfer coefficients between the compartments has been developed considering material balance among the compartments in biosphere and then implementing to AMBER, a general and flexible software tool that allows to build dynamic compartment models. An illustrative calculation with ACBIO is shown.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.1
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• pp.91-99
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• 2007

It was intended in this study to investigate the effects of various parameters on the chemical reaction or mass transfer yield in a tubular-type nuclear waste treatment equipment. Since such equipments, as a tubular reactor, multistage solvent extractor, and adsorption column, accompany chemical reaction or mass transfer along the fluid-flowing direction, mathematical modeling for each equipment was carried out first. Then their behaviors of the chemical reaction or mass transfer were predicted through computer simulations. The inherent major parameters for each equipment were chosen and their sensitivities. affecting the reaction or mass transfer yield were analyzed. For the tubular reactor, the effects of axial diffusion coefficient and reaction rate constant on the reaction yield were investigated. As for the multistage solvent extractor, the backmixing of continuous phase and the distribution coefficient between fluid and solvent were considered as the major parameters affecting the extraction yield as well as concentration profiles throughout the axial direction of the extractor. For the adsorption column, the equilibrium constant between fluid and adsorbent surface, and the overall mass transfer coefficient between the two phases were taken as the major factors that affect the adsorption rate.

• Science of Emotion and Sensibility
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• v.13 no.4
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• pp.687-692
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• 2010

This paper surveys emission characteristics of Far-infrared of the fabrics fabricated with germanium imbedded sheath-core conjugate composite filaments. For this purpose, master batch chip was prepared with PET semi-dull chip and nano sized germanium particles and sheath-core type conjugate composite filament was spun using this master batch chip and polyester semi dull. The emission power and emissivity of the germanium imbedded fabrics were measured and investigated using FT-IR spectrophotometer by KICM- FIR 1005 measurement method. In addition, the fabric mechanical properties were measured and discussed with the effects of the optimum texturing process conditions and fabric structural design conditions. The sheath/core type PET composite germanium imbedded filaments were manufactured by the optimum spinning condition, its tenacity and breaking strain showed the same level as the regular PET filament. The tenacity and breaking strain of the DTY showed good physical properties and no problem in the weaving process. Then, wet and dry shrinkages showed higher values than those of regular PET filament. The emission power of the germanium imbedded fabric was $3.53{\times}10^2W/m^2$ at the $5-20{\mu}m$ wave length range, and emissivity was 0.874. The fabric hand of germanium imbedded fabrics was inhanced by the optimum texturing process and fabric structural design with improved mechanical properties such as fabric bending and compressional properties.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.385-390
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• 1998

방사성 페이온교환수지 아스팔트고화체를 처분장 등지에서 장기간 저장시 안전성 확보를 위하여 물리적 강도가 높고 고화체내에서 방사성핵종의 침출저항성 및 처리시 감용의 효과가 우수한 고화체 연구가 필요하게 되었다. 실험에 사용된 이온교환수지는 입상형 양이온 교환수지를 대상으로 하였으며 고화매질로서는 도로포장용으로 생산되는 직류아스팔트 60/70을 사용하였다. 고화보조제는 방사성 고체패기물 포장시 사용되어 폐기물로 발생되는 페폴리에틸렌(폐PE) 필름을 사용하였다. 실험결과 고화체의 형태안정성은 PE 함유량이 10 wt% 이상일 때 고화체 형태를 그대로 유지할 수 있으며 압축강도는 414 kPa(60 psi) 이상을 나타내었다. 최적의 운전조건은 이온교환수지, PE 함유량이 건조기준으로 각각 30~50 wt%, 10~25 wt% 이며, 고화온도는 170~20$0^{\circ}C$이다. 고화체의 침출특성은 확산 (diffusion) 으로 해석이 가능하며, 유효확산계수(De)는 Cs, Co의 경우 각각 1.621$\times$$10^{-7}$, 1.186$\times$$10^{-9}$ $\textrm{cm}^2$/day로 나타나고, Leachablity index는 각각 11.7, 13.8로 미국 원자력위원회 (NRC)가 요구하는 기준값 6보다 훨씬 높게 나타났다.