우울증 환자 치료에 있어서 Tianeptine과 Sertraline의 효과와 안전성 비교

이민수,강성민,기백석,연병길,오병훈,이철,채정민,백인호 大韓神經精神醫學會 2001 신경정신의학 Vol.40 No.2

연구목적: 주요 우울증의 치료에 있어서 티아넵틴과 써트랄린의 임상적 효과와 안정성을 비교하기 위하여 연구를 시행하였다. 방법: DSM-IV 진단 기준에 의거하여 주요 우울증의 진단기준에 부합되고 17항목 해밀턴 우울척도 점수가 14점 이상인 환자를 대상으로 하였다. 총 40명의 환자를 무작위적 방식에 따라 티아넵틴 치료군과 써트랄린 치료군으로 분류하였다. 선탠된 환자에서 다른 항우울제를 복용하고 있는 경우 7일 이상의 약물 배설기간을 가진 후 티아넵틴과 써트랄린을 각각 6주간 투여하였으며, 기준점, 1주후, 2주 후, 4주 후, 6주 후에 HAM-D, MADRS, 그리고 CGI, COVI 등을 사용하여 평가하였다. 본 연구기간 중 발생된 모든 부작용은 부작용의 발생 및 소실 시기, 심한 정도, 발생 빈도, 관련 조치 및 결과에 대하여 증례기록서에 기록하도록 하였다. 결과: 30명(티아넵틴군 15명 ; 써트랄린군 15명)이 6주간의 연구를 완결하였고 티아넵틴 치료군에서는 1일 37.5mg을 투여하였으며 써트랄린군에서는 1일 평균 64.0±22.5mg을 투여하였다. 본 연구 결과 HAM-D, MADRS, CGI 상에서 두 군 모두에서 치료 1주 후부터 유의한 감소를 나타내었으며 이는 2주 후, 4주 후, 6주 후에도 지속적인 감소를 보였고 두 군간에 항우울 효과의 차이는 없었다. 활력징후, 일반 혈액학, 생화학, 심전도 검사 등에서는 두 군 모두 유의한 변화는 없었다. 티아넵틴과 관련된 부작용으로 흔히 보고한 증상은 오심(33.3%), 복부 불쾌감(26.7%), 구강 건조(20.0%), 두통(13.3%)등 이었고 써트랄린 치료군에서는 구강 건조(53.3%), 두통(46.7%), 오심(33.3%), 그리고 식욕 부진(33.3%)등으로 티아넵틴군에서 보다 적은 발현빈도를 보였다. 결론: 티아넵틴은 우울증의 치료에 있어서 효과적이고, 내약성이 우수한, 안전한 항우울제이다. Objective: This study was designed to evaluate the efficacy and safety of tianeptine and sertraline in the treatment of patients with depression. Method: The study was done on the patients with major depression diagnosed by DSM-IV, who had aHamilton Rating Scale for Depression(HAM-D) score ≥ 14 on the first 17 items of the HAM-D. A total of 40 patients were randomly assigned to tianeptine group and sertraline group. Tianeptine and sertraline were prescribed to each group. 6 weeks of each medication was carried out after 7 days of drug excretion period. Evaluation using 17 item HAM-D, Montgomery and Åsberg Depression Rating Scale(MADRS), Clinical Global Impression Scale (CGI), and Covi Scale was done on the baseline and after 1 week, 2 weeks, 4 weeks, and 6 weeks. Regrding all side effects that had occurred during the period of our study such as their developed/disappeaed time, severitien, incidences, managements and results have been recorded. Results: A total of 30 patients(tianeptine group 15 ; sertraline froup 15) finished the 6 weeks of research. 37.5mg of the daily dose was regularly prescribed to the tianeptine group, the average amount of 64.0±22.5mg of the final daily dose was prescribed to the sertraline group. Total 17 item HAM-D scores, total points of MADRS and CGI showed significant decrease after 1 week in each treatment froup and continous decrease after 2, 4 and 6 weeks ; and no difference was found between tianeptine group and sertaline group in the antidepressant efficacy. Also there were no significant changes in vital sign, CBC, chemistry, and EKG in each treatment group. The common reported side effects of tianeptine were nausea(33.3%), epigastic distress(26.7%), dry mouth(20.0%), headache(13.3%) and those of sertraline were dry mouth (53.3%), headache(46.7%), nausea(33.3%), anorexia(33.3%). Conclusion: According to the results, tianeptine was effective in improvement of depressive symptoms and was well tolerated and safe in patients with depression.

열복사의 색수차 공간여과를 이용한 레이저 용접 감시기술

김민석,백성훈,박승규,정진만,김철중 한국레이저가공학회 1999 한국레이저가공학회지 Vol.2 No.2

An innovative real-time weld monitoring technique using chromatic filtering of the thermal radiation from a weld pool is developed. This thermal radiation from the weld pool is focused on an aperture and the transmitted thermal radiation is monitored at two wavelengths with high-speed single-element detectors. Due to the chromatic aberration introduced in the focusing optics, the transmittance curve of thermal radiation varies by the wavelength. Owing to this difference in the transmittance, the local variation of thermal radiation from the weld pool can be monitored by processing the two spectroscopic signals from two detectors. In this paper, the algorithms to monitor the laser power on the weld specimen and the focus shift are investigated and the performances of laser power and focus monitoring are shown for a pulsed Nd:YAG laser welding. The monitoring of the weld pool size variation is also discussed.

Systolic Array를 이용한 2차원 CMT

朴敏植,金英百,郭勳星 전북대학교 전자산업개발연구소 1990 전자산업연구 Vol.1 No.-

This paper proposes systolic array for 2-D C-Matrix Transtorm(CMT). Compared the conventional method with the proposed 2-D CMT without matrix transpolsition, it is required the more PE's, but the less latency. Also, it is shown that the systolic array VLSI implementation for 2-D CMT is feasible.

압입유동특성 평가를 위한 진변형률 정의에 관한 고찰

전은채,백민경,김성훈,박주승,권동일 대한금속재료학회 2004 대한금속·재료학회지 Vol.42 No.12

Continuous indentation test is getting more used to derive indentation flow curve. The overall deriving algorithm is relatively well-established, the details of the algorithm are, however, still argued. One of the arguments is the definition of true strain which constitutes the indentation flow curve. In this study, work-hardening exponent was adopted for determining what definition is appropriate to obtain accurate indentation flow curve since work-hardening exponent is affected by only the definition of true strain not by other constants. The effect of calibrating contact depth was eliminated using finite element analysis. Finally, the definition based on tangent function was determined to be proper for deriving the indentation flow curve. (Received September 8, 2004)

전방 또는 전측방 흉수 종양 수술에서 후측방도달법

조경석,박춘근,성재훈,허필우,박춘근,백민우,김달수,강준기 대한신경외과학회 1997 Journal of Korean neurosurgical society Vol.26 No.5

Sorptionof Eu(III) Th(IV) on Bentonite Colloids Considering Their Precipitation an Colloid Formation

Min-Hoon Baik,Jae-Kwang Lee,Seung-Yeop Lee,Seung-Soo Kim 한국방사성폐기물학회 2008 방사성폐기물학회지 Vol.6 No.2

본 연구에서는 국내산 경주벤토나이트를 이용하여 제조한 벤토나이트 콜로이드에 대한 산화환원 반응에 대체적으로 안정한 다가 핵종인 Eu(III)와 Th(IV)의 실험적 수착 연구를 수행하였다. 수착실험에 대한 공시험을 수행하여 반응용기 벽면에 의해, 침전에 의해, 콜로이드 형성에 의해 손실된 핵종들의 양을 평가하였다. 그리고 이러한 손실들을 반영한 Eu(III)와 Th(IV)의 벤토나이트 콜로이드에 대한 수착분배계수 값을 구하고 조사하였다. 세 종류의 손실양을 반영한 벤토나이트 콜로이드의 순수한 수착분배계수 값은 pH 변화에 따라 Eu(III)의 경우 정도의 값을 가지고, Th(IV)의 경우 정도의 값을 가지는 것으로 관측되었다. 특히 Eu(III)의 경우엔 pH 5 이상에서 침전의 영향이 크게 나타났고, Th(IV)의 경우엔 pH 3 이후에 콜로이드 형성과 침전의 영향이 크게 나타났다. 따라서 주어진 농도에서 콜로이드 형성 및 침전 영향이 커지는 pH 이후에는 Eu(III) 및 Th(IV)과 같은 다가 핵종들의 정확한 수착분배계수를 구하기 위해서는 이러한 침전 및 콜로이드 형성과 같은 영향이 반영되어야 할 것이다. In this study, a sorption experiment of multivalent nuclides such as Eu(III) and Th(IV) relatively stable for redox reactions was carried out for bentonite colloids which had been prepared from the domestic Gyeongju bentonite. The amounts of the nuclides lost by an attachment to bottle walls, by a precipitation, and by a colloid formation were estimated by performing blank tests for the sorption experiments. Sorption coefficients, , reflecting the mass losses were obtained and investigated for the sorption of Eu(III) and Th(IV) onto the bentonite colloids. The net sorption coefficients considering all the three mass losses were measured as about and for Eu(III) and Th(IV), respectively, depending on pH. In particular, a precipitation occurred mainly at a pH greater than 5 for Eu(III) and a precipitation and colloid formation significantly occurred at a pH greater than 3 for Th(IV). The precipitation and colloid formation of the multivalent nuclides of Eu(III) and Th(IV) therefore should be considered when are rightly obtained over the pH range where their precipitation and colloid formation become significant at a given concentration.

An Experimental Study on the Sorption of Uranium(VI) onto a Bentonite Colloid

Min-Hoon Baik,Won Jin Cho 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.3

본 연구에서는 현재 국내에서 고준위 방사성폐기물 처분장의 잠재적인 완충재 물질로 고려되고 있는 경주벤토나이트에서 발생 가능한 벤토나이트 콜로이드로의 우라늄(VI) 수착특성에 대한 실험적 연구를 pH 및 이온강도의 함수로 수행하였다. 경주벤토나이트로부터 분리된 콜로이드는 주로 몬모릴로나이트로 구성되어 있다. 중력여과법을 사용하여 측정한 결과 농도 및 크기는 약 5100 ppm 및 200-450 nm 이었다 우라늄 수착실험에 대한 공시험을 수행하여 수착 반응용기 벽면에 흡착, 침전, 한외여과에 의해 손실된 우라늄 양을 평가하였다. 이러한 과정에 의해 제거된 우라늄의 양은 미량이었다. 그러나 한외여과에 의한 우라늄 손실의 경우 이온강도가 낮은 경우 즉, 0.001 M 의 경우 한외여과 필터의 표면전하 역전에 의한 양이온 수착 영향으로 인해 매우 높은 핵종 손실을 유발하였다. 벤토나이트 콜로이드에 대한 우라늄(VI)의 수착 분배계수 (또는 의사콜로이드 형성상수)는 PH 및 이온강도에 따라 값을 가지며 pH 중성영역인 6.5 근처에서 최대값을 가지는 것으로 나타났다. 벤토나이트에 대한 우라늄(VI)의 수착은 pH, 이온강도, 탄산농도 등과 같은 지화학적 변수들에 의존하는 수용액에서 우라늄화학종과 매우 밀접한 관련이 있다 따라서 벤토나이트 완충재로부터 발생된 벤토나이트 콜로이드는 높은 수착능으로 인해 우라늄(VI)을 의사콜로이드(pseudo-colloid)의 형태로 지질학적 매질을 통해 이동시킬 수 있을 것이다. In this study, an experimental study on the sorption properties of uranium(VI) onto a bentonite colloid generated from Gyeongju bentonite which is a potential buffer material in a high-level radioactive waste repository was performed as a function of the pH and the ionic strength. The bentonite colloid prepared by separating a colloidal fraction was mainly composed of montmorillonite. The concentration and the size fraction of the prepared bentonite colloid measured using a gravitational filtration method was about 5100 ppm and 200-450 nm in diameter, respectively. The amount of uranium removed by the sorption reaction bottle walls, by precipitation, and by ultrafiltration was analyzed by carrying out some blank tests. The removed amount of uranium was found not to be significant except the case of ultrafiltration at 0.001 M . The ultrafiltration was significant in the lower ionic strength of 0.001 M due to the cationic sorption onto the ultrafilter by a surface charge reversion. The distribution coefficient (or pseudo-colloid formation constant) of uranium(VI) for the bentonite colloid was about depending upon pH and ionic strength of and the was highest in the neutral pH around 6.5. It is noted that the sorption of uranium(VI) onto the bentonite colloid is closely related with aqueous species of uranium depending upon geochemical parameters such as pH, ionic strength, and carbonate concentration. As a consequence, the bentonite colloids generated from a bentonite buffer can mobilize the uranium(VI) as a colloidal form through geological media due to their high sorption capacity.

A Theoretical Approach on the Migration of a Chelating Radionuclide in Porous Medium

Baik,Min-Hoon,Lee,Kun-Jai 대한방사선 방어학회 1992 방사선방어학회지 Vol.17 No.2

이온 또는 착화된 상태의 방사성핵종의 이동에 대한 착화제의 영향을 조사하기 위하여 새로운 모델이 제시되었다. 착화된 방사성핵종의 이동거동은 착화제와 착화된 방사성핵종의 열화를 포함하는 대류-확산 이동방정식에 의해 해석되었다. 이 수학적 모델은 해석적인 방법에 의해 구해졌으며 지연요소를 조사함으로써 분석되었다. 계산결과들은 감소된 지연요소에 의해 착화된 방사성핵종의 이동속도가 이온형태의 방사성핵종보다 매우 빠름을 보여주었다. 따라서 원자력발전소로부터의 착화제의 발생과 환경으로의 유출을 감소시킬 수 있는 새로운 구제책이 필요하다고 하겠다. A new model was developed in order to investigate the effects of chelating agents on the migration of a radionuclide in the from of ion or chelate. The migration behavior of the chelated radionuclide was analyzed by formulating a convective-dispersion transport equation which included a degradation of chelating agent and chelated radionuclide. The mathematical model was analytically solved and checked with the existing retardation factor. The results show that the migration velocity of the chelated radionuclide was much faster than the ionic one due to the decreased retardation. Therefore, it was concluded that a new remedial action should be developed to reduce the generation and release of chelating agents from the nuclear power plant into the environment.

Confidence Improvement of Disposal Safety by Development of a Safety Case for High-Level Radioactive Waste Disposal

Min Hoon Baik,Nak-Youl Ko,Jongtae Jeong,Kyung-Su Kim 한국방사성폐기물학회 2016 방사성폐기물학회지 Vol.14 No.4

고준위방사성폐기물 심층처분에서 처분안전성의 신뢰도를 향상시킬 수 있는 방안으로 그리고 처분 프로그램 개발 및 인허가를 위해 많은 나라들에서 자국에 적합한 safety case를 개발하고 있다. 본 연구에서는 방사성폐기물 처분을 위한 safety case 의 의의, 필요성, 개발과정들을 정리하고 소개하였다. 그리고 처분안전성을 safety case의 다양한 측면에서 논의하였다. 아울러 스위스, 일본, 미국, 스웨덴, 핀란드 등 해외의 safety case 개발 현황과 현재 KAERI에서 개발 중인 safety case의 개발전략을 간략히 소개하였다. 고준위방사성폐기물 처분안전성의 신뢰도 향상을 위해 safety case 기반 하에서 어떤 노력들이필요한지를 분석하였다. 그리고 국내 상황을 반영하여 신뢰할 수 있는 정보자료의 구축, 안전성 관련 과정들의 이해, 안전성평가의 불확실성 저감, 이해당사자와의 의사소통, 공정성과 투명성 확보 등의 실행 방안을 제안하고 논의하였다. 본 논문에제시된 내용들은 심층처분 safety case를 이해하고, 국내에서 개발하고 있는 고준위방사성폐기물 처분 safety case 개발을 통한 처분안전성 신뢰도 향상에 기여할 수 있을 것으로 기대한다. Many countries have developed a safety case suitable to their own countries in order to improve the confidence of disposal safety in deep geological disposal of high-level radioactive waste as well as to develop a disposal program and obtain its license. This study introduces and summarizes the meaning, necessity, and development process of the safety case for radioactive waste disposal. The disposal safety is also discussed in various aspects of the safety case. In addition, the status of safety case development in the foreign countries is briefly introduced for Switzerland, Japan, the United States of America, Sweden, and Finland. The strategy for the safety case development that is being developed by KAERI is also briefly introduced. Based on the safety case, we analyze the efforts necessary to improve confidence in disposal safety for high-level radioactive waste. Considering domestic situations, we propose and discuss some implementing methods for the improvement of disposal safety, such as construction of a reliable information database, understanding of processes related to safety, reduction of uncertainties in safety assessment, communication with stakeholders, and ensuring justice and transparency. This study will contribute to the understanding of the safety case for deep geological disposal and to improving confidence in disposal safety through the development of the safety case in Korea for the disposal of high-level radioactive waste.

A Geochemical Study on the Uranium Mobility in a Deep Geological Repository: A Natural Analogue Approach Using a Uranium Deposit in the Ogcheon Metamorphic Belt

Min-Hoon Baik,YeoJin Ju,Dawoon Jeong,Ji-Hun Ryu 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1

The mobility of uranium (U) in the environment of a deep geological repository is controlled by various geochemical conditions and parameters. In particular, oxidation state of uranium is considered as a major factor to control the mobility of uranium in most of geological environments. In this study, therefore, we investigated the mobility of uranium in a deep geological repository by a natural analogue approach using a uranium deposit in the Ogcheon Metamorphic Belt (OMB). Uranium contents of rock samples from the study site ranged from 1.3 to 71 ppm (average 17.4 ppm). Uranium minerals found in the study site were mostly uraninite (UIVO2+x) and uranothorite ((UIV, Th)SiO4). The concentrations of U in the groundwater samples were very low (0.025~0.690 ppb) even though redox conditions are weakly oxidizing. Calculation results for U speciation in groundwater samples showed that major dissolved uranium species in the groundwater samples are mainly as calcium uranyl (UO2 2+) carbonate complexes such as Ca2UO2(CO3)3(aq) and CaUO2(CO3)3 2-. However, the activity ratios between 234U and 238U (AR(234U/238U)) showed U behavior in reducing conditions although the groundwater conditions were not reducing conditions and major dissolved U species were U(VI) species. Results from electron microscopic analyses for rock samples showed that major uranium minerals were U(IV) minerals such as uraninite and uranothorite. We could not identify other uranyl minerals and altered minerals from uraninite. This means that the geochemical condition of the study site has been maintained a reducing condition although the groundwater condition was a weakly oxidizing condition. Thus, the dissolution of uranium is strongly limited by the low solubility of uraninite. It is not obvious how the reducing condition of the study site has been maintained. Reducing agents such as pyrite, organic materials, and reducing bacteria might contribute to maintaining the reducing condition although further studies will be necessary. Results from this study imply that uranium mobility will be greatly limited by low dissolution of uraninite into groundwater if the reducing condition is well reserved. This limited mobility of uranium will be also contributed by low possibility of uraninite alteration into uranyl minerals which have a higher solubility than uraninite.