• 대한임상검사과학회지
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• 제51권3호
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• pp.301-308
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• 2019

다제내성 P. aeruginosa의 출현과 확산은 전 세계적으로 중요한 문제가 되고 있다. P. aeruginosa에 의한 발병은 일부 몇몇 세포 관련 및 세포외 병독성 인자의 생성에 기인한다. 본 연구에서는 대전지역의 3차 병원에서 분리된 carbapenem 내성 P. aeruginosa를 대상으로 병독성 인자의 분포와 항균제 내성 양상을 조사하였다. 항균제 감수성 시험은 디스크 확산법으로 확인하였고, 병독성 유전자의 분석을 위해 PCR과 염기서열분석을 수행하였다. 또한, 다제내성 P. aeruginosa의 sequence type (ST)은 multilocus sequence typing (MLST)을 통해 확인하였다. 32균주의 carbapenem 내성 P. aeruginosa 중, 14균주(43.8%)가 다제내성이었으며, 주요 ST는 ST235 (10균주, 71.4.%)임을 확인하였다. 병독성 유전자는 32균주 모두에서 확인되었고, 이 중 가장 높은 빈도로 확인된 병독성 유전자는 toxA, plcN, phzM (100.%)이었다. 또한, 32균주는 모두 8개 이상의 병독성 유전자를 가지고 있었으며, 9균주(28.1%)가 15개의 병독성 유전자를 가지고 있었다. exoU 유전자는 다제내성 P. aeruginosa 균주의 71.4%에서 확인되었다. 이러한 결과는 exoU 유전자가 다제내성 P. aeruginosa 균주의 지속성에 대한 예측 표지자가 될 수 있을 것으로 사료된다.

• 경영과학
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• 제11권2호
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• pp.207-235
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• 1994

Regarding the study in innovation/R&D programs evaluation, twelve cases from the U.S ., U. K., Germany, France, Sweden, Australia, Japan, and EC are analyzed, and its implications to Korean situation are investigated. From the analysis of the cases, some valuable guidelines for Korea are developed. Some of the guidelines are: the evaluation must be treated as an integral part of the Government supported programs, specialists in evaluation should be raised, the long-term effects and non-economic/social effects should also be included in the evaluation, various efforts to acquire more exact and versatile information necessary for quality evaluation should be made, and additional effort is required for the evaluation to be actualized.

• 한국생물공학회:학술대회논문집
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• 한국생물공학회 2002년도 생물공학의 동향 (X)
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• pp.211-214
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• 2002

The optimal condition for the production of DXAMase, containing the both characteristics of dextranase and amylase, was studied based on different levels of pH, temperature, and aeration rate. Response surface methodology was applied to find the optimatic condition showing the relationship between the fermentation response(dextranase and amylase activity of DXAMase) and the fermentation variables(pH, temperature, and agitation rate). In case of dextranase activity, the condition of pH 4.06, $28.08^{\circ}C$, and 235.14 rpm showed the highest activity, 2.26 U/ml, and for amylase activity, the condition of pH 4.01, $27.96^{\circ}C$, and 212.01 rpm showed the highest activity, 3.52 U/ml. For the production of DXAMase, dextranase and amylase, the optimum condition was pH 4.06, $28.08^{\circ}C$, and 234.80 rpm.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.156-165
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• 2001

A radiological safety assessment was performed for a hypothetical near-surface radioactive waste repository as a simple screening calculation to identify important nuclides and to provide insights on the data needs for a successful demonstration of compliance. Individual effective doses were calculated for a conservative ground water pathway scenario considering well drilling near the site boundary. Sensitivity of resulting ingestion dose to input parameter values was also analyzed using Monte Carlo sampling. Considering peak dose rate and assessment time scale, C-14 and T-129 were identified as important nuclides and U-235 and U-238 as potentially important nuclides. For C-14, the dose was most sensitive to Darcy velocity in aquifer The distribution coefficient showed high degree of sensitivity for I-129 release.

• Nuclear Engineering and Technology
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• 제33권4호
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• pp.375-385
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• 2001

The total burnup in the spent U$_3$Si/Al fuel samples from Hanaro reactor was determined by destructive methods using $^{148}$ Nd, the sum of $^{143}$ Nd and $^{144}$ Nd, the sum of $^{145}$ Nd and $^{146}$ Nd, and the sum of total Nd isotopes($^{143}$ Nd, $^{144}$ Nd, $^{145}$ Nd, $^{146}$ Nd, $^{148}$ Nd and $^{150}$ Nd) monitors. The fractional($^{235}$ U) turnup in the spent fuel samples was also determined by U and Pu mass spectrometric method. The samples were dissolved in a mixture of 4 M HCI and 10 M HNO$_3$ without any catalyst. The separation of U, Pu and Nd from the spiked and unspiked sample solutions was achieved by two sequential anion exchange separation methods. The isotope compositions of these elements, after their separation from the fuel samples were measured by mass spectrometry. The contents of the elements in the spent fuel samples were determined by isotope dilution mass spectrometric method(IDMS) using $^{233}$ U, $^{242}$ Pu and $^{150}$ Nd as spikes. The effective fission yield was calculated from the weighted fission yields averaged over the irradiation period. The difference between total turnup values determined by various Nd monitors were in the range of 1.8%.

• Advances in concrete construction
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• 제9권3호
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• pp.235-248
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• 2020

Progressive collapse in a structure occurs when load bearing members are failed and the adjoining structural elements cannot resist the redistributed forces and fails subsequently, that leads to complete collapse of structure. Recently, construction using precast concrete technology is adopted increasingly because it offers many advantages like faster construction, less requirement of skilled labours at site, reduced formwork and scaffolding, massive production with reduced amount of construction waste, better quality and better surface finishing as compared to conventional reinforced concrete construction. Connections are the critical elements for any precast structure, because in past, major collapse of precast structure took place because of connection failure. In this study, behavior of four different precast wet connections with U shaped reinforcement bars provided at different locations is evaluated. Reduced 1/3^rd scale precast beam column assemblies having two span beam and three columns with removed middle column are constructed and examined by performing experiments. The response of precast connections is compared with monolithic connection, under column removal scenario. The connection region of test specimens are filled by cast-in-place micro concrete with and without polypropylene fibers. Performance of specimen is evaluated on the basis of ultimate load carrying capacity, maximum deflection at the location of removed middle column, crack formation and failure propagation. Further, Finite element (FE) analysis is carried out for validation of experimental studies and understanding the performance of structural components. Monolithic and precast beam column assemblies are modeled using non-linear Finite Element (FE) analysis based software ABAQUS. Actual experimental conditions are simulated using appropriate boundary and loading conditions. Finite Element simulation results in terms of load versus deflection are compared with that of experimental study. The nonlinear FE analysis results shows good agreement with experimental results.

• 한국식품영양학회지
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• 제11권1호
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• pp.6-10
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• 1998

탈취온도가 옥수수기름의 냉각시험 및 발연점에 미치는 영향을 측정해 보았다. 탈취온도가 상승할수록 투입되는 탈납유 대비 탈취유의 냉각시험 결과는 현저히 하락하였으며, 26$0^{\circ}C$ 이상에서는 그 정도가 극심하여 이는 포화도 증가 및 SU2, S2U, S3형 triglycerides 함량 증가와 상관관계가 있는 것으로 추측되었다. 한편, 발연점은 탈취온도 24$0^{\circ}C$에서 가장 높은 242$^{\circ}C$를 나타내었고, 탈취온도 245~27$0^{\circ}C$의 범위에서는 235~238$^{\circ}C$로 하락하였으며, 이러한 현상은 시료유의 산값과 반비례하는 것으로 나타났다. 따라서 일반 이화학적 특성, 지방산 조성 등과 함께 냉각시험 및 발연점에서도 고온탈취는 악영향을 미치는 것으로 판명되었다.

• 콘크리트학회논문집
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• 제28권2호
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• pp.235-244
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• 2016

본 논문에서는 고강도콘크리트와 SD600 철근을 적용한 특수모멘트골조의 최상층 접합부 내진성능을 파악하고자 한다. 실험체 중 K-RC-H는 내진규정에 따라 제작되었으며, K-HPFRC-H에는 횡보강근 간격을 150%로 증가시키면서 대신 강섬유를 부피비 1.0% 혼입하였다. K-RC-H, K-HPFRC-H 실험체 모두 주근이 파단하기 이전까지 내력 저하가 거의 없었고 에너지 소산능력 등에서 우수한 내진성능을 보였다. 접합부내의 U-bar는 보 주근이 휨과 함께 인장력을 받을 때 상부면으로 밀어내려는 현상을 충분히 억제하는 것으로 나타났다. 한편 SD600의 정착길이는 $1.25l_{dt}$가 확보되었는데 슬립거동이 거의 발생하지 않았다. 전반적으로 강섬유의 혼입은 휨강도 증가, 전단변형각 구속력 향상 등에 기여하였고, 강섬유 혼입률 1.0% 혼입함으로써 횡보강근 간격을 1.5배 증가시킬 수 있는 가능성을 실험적으로 확인하였다.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.613-623
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• 2016

Molybdenum-99 ($^{99}Mo$) is the most important isotope because its daughter isotope, technetium-99m ($^{99m}Tc$), has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of $^{99}Mo$, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of $^{99}Mo$ technology developments. Most of the industrial-scale $^{99}Mo$ processes have been based on the fission of $^{235}U$. Recently, important issues have been raised for the conversion of fission $^{99}Mo$ targets from highly enriched uranium to low enriched uranium (LEU). The development of new LEU targets with higher density was requested to compensate for the loss of $^{99}Mo$ yield, caused by a significant reduction of $^{235}U$ enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission $^{99}Mo$ production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the $^{99}Mo$ production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

• Nuclear Engineering and Technology
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• 제11권4호
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• pp.295-301
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• 1979

열중성자에 의한 $U^{235}$의 핵분열 시에 가벼운 쪽 핵분열 생성물의 핵전하 분포를 질량수에 따라 계산했다. 1차 핵분열 생성물의 핵전하 분포를 계산해서 실험치와의 비교를 통해, 지금까지 게시된 핵분열 조각의 핵전하 분포를 결정하는 이론의 타당성을 검토한 결과 어느 이론도 핵분열 조각의 핵전하 분포를 정확하게 기술할 수 없는 것이 판명됐다. 핵분열 조각의 최빈전하 ($Z_{P}$)와 불변전하밀도($Z_{UCD}$, UCD : Unchanged Charge Density)와의 차이는 0.45~0.5 사이로 질량수에 따라 크게 변동하지 않음을 보여준다. 핵분열 조각의 핵전하 분포에서 분산도를 나타내는 표준편차 ($\sigma$)는 ~0.5의 값을 갖는 것으로 나타났다. 핵분열 생성물에서 중성자의 Odd-Even 효과가 나타나려면, 즉발중성자 방출확률에도 Odd-Even 효과가 나타나야 한다는 결론을 얻었다.