혈액 종양환자에서 Tobramycin의 임상약동학

신재국,신완균,장인진,신상구,김성민,배현주,최강원,김진규 대한화학요법학회 1990 대한화학요법학회지 Vol.8 No.1

항암화학요법을 받고 있던 중 감염으로 tobramycin을 투여받은 36명의 혈액종양 환자에서 tobramycin의 약동학적 특성을 비종양환자군에서의 population 값과 비교 검토하였다. 이들은 모두 정상 신기능을 가진 16세 이상의 성인남녀(21:15)백혈병 환자들이었다. 36명의 혈액종양 환자에서 산출된 tobramycin의 청소율 및 체내분포용적은 각각 120.3± 27.2ml/lg/hr 및 0.386± 0.11 L/㎏로 population 추정 치보다 유의하게 큰 값을 보였다.(P. <0.05).청소율과 체내분포용적을 해당 population 추정치로 나눈 비율치(ratio)의 평균값은 각각 1.47± 0.34 및 1.20± 0.34였다. 연령, hematocrit치, 혈청albumin치, 발열 및 항암화학요법기간과 tobramycin의 청소율 및 체내분포용적 사이에 유의한 상관관계는 발견할 수 없었다. 본 연구결과 혈액종양 환자에서 tobramycin 투여시는 적정혈장농도를 유지하기 위해 일반 환자군에 비해 용량의 증가 및 투여간격의 조정이 필요하며 지속적인 혈장농도 monitoring을 통하여 용법의 재적정화가 필요할 것으로 사료된다. The pharmacokinetics of tobramycin were evaluated in 36 hematologic malignancy patients undergoing anticancer chemotherapy and compared to the expected values from the population parameters. Total body clearance(mean : 12.3±27.2㎖/㎏/hr) and volume of distribution (mean : 0.386±0.11 L/㎏) in hematologic malignancy patients with normal renal function were significantly greater than those of estimated from population parameter distribution(P<0.05). The ratios of total body clearance and volume of distribution to the population estimates were 1.44±0.37 and 1.20±.034, respectively. No relationships were found between age, hematocrit, serum albumin, fever or duration of anticancer chemotherapy and pharmacokinetic parameters. It is suggested that the increment of tobramycin dose regimen wold be considered in patients with hematologic malignancy, and dose readjustment followed by close monitoring of plasma drug concentration would be required.

홍국균의 최적배양조건에 관한 연구

정순택,임종환,박양균,황금택,박현진,안찬영,강성국,문길만 木浦大學校 工業技術硏究所 1994 工業技術硏究誌 Vol.4 No.-

Cell growth and pigment productivity of Monascus anka KCCM 11832 and Monascus sp. has isolated from the Korean Maeju(soybean koji) were determined for effect of culture medium composition and incubation conditions. Increase of NH₄NO₃, and KH₂PO₄ concentration as mineral source promoted mycelium growth, and the highest cell growth was showed in the medium with 0.05% KH₂PO₄ when C/N ratio is 20:1, but pigment production was significantly inhibited at higher concentration than this level. Cell growth and pigment production in porato dextrose medium were higher than those in czapeck-dox broth and malt extract medium. In terms of temperature, the highest cell growth was showed at 34℃, but pigment productivity was the highest at 26℃.

AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

Kang, Hyun-Gook,Kim, Man-Cheol,Lee, Seung-Jun,Lee, Ho-Jung,Eom, Heung-Seop,Choi, Jong-Gyun,Jang, Seung-Cheol Korean Nuclear Society 2009 Nuclear Engineering and Technology Vol.41 No.6

Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.

Development of Automatic Reactor Internal Vibration Monitoring System Using Fuzzy Peak Detection and Vibration Mode Decision Method

Hyun Gook Kang 한국원자력학회 1998 Nuclear Engineering and Technology Vol.30 No.1

Development of a Real-Time Thermal Performance Diagnostic Monitoring System Using Self-Organizing Neural Network for KORI-2 Nuclear Power Unit

Kang, Hyun-Gook,Seong, Poong-Hyun Korean Nuclear Society 1996 Nuclear Engineering and Technology Vol.28 No.1

In this work, a PC-based thermal performance monitoring system is developed for the nuclear power plants. The system performs real-time thermal performance monitoring and diagnosis during plant operation. Specifically, a prototype for the KORI-2 nuclear power unit is developed and examined in this work. The analysis and the fault identification of the thermal cycle of a nuclear power plant is very difficult because the system structure is highly complex and the components are very much inter-related. In this study, some major diagnostic performance parameters are selected in order to represent the thermal cycle effectively and to reduce the computing time. The Fuzzy ARTMAP, a self-organizing neural network, is used to recognize the characteristic pattern change of the performance parameters in abnormal situation. By examination, this algorithm is shown to be able to detect abnormality and to identify the fault component or the change of system operation condition successfully. For the convenience of operators, a graphical user interface is also constructed in this work.

Development of Automatic Reactor Internal Vibration Monitoring System Using Fuzzy Peak Detection and Vibration Mode Decision Method

Kang, Hyun-Gook,Seong, Poong-Hyun,Park, Heui-Youn,Lee, Cheol-Kwon,Koo, In-Soo Korean Nuclear Society 1998 Nuclear Engineering and Technology Vol.30 No.1

In this work a method to detect the vibrational peak and to decide the vibrational mode of detected peak for core internal vibration monitoring system which is particularly concerned on the core support barrel (CSB) and fuel assemblies is developed. Flow induced vibration and aging process in the reactor internals cause unsoundness of the internal structure. In order to monitor the vibrational status of core internal, signals from the ex-core neutron detectors are transformed into frequency domain. By analyzing transformed frequency domain signal, an analyst can acquire the information on the vibrational characteristics of the structures, i.e., vibration frequencies of each component, vibrational level, modes of vibration, and the causes of the abnormal vibration, if any. This study is focused on the development of the automated monitoring system. Several methods are surveyed to define the peaks in power spectrum and fuzzy theory is used to automatic detection of the vibrational peaks. Fuzzy algorithm is adopted to define the modes of vibration using the peak values from fuzzy peak recognition, phase spectrum, and coherence spectrum.

Application of Smart Transmitter Technology in Nuclear Engineering Measurements

Kang, Hyun-Gook,Seong, Poong-Hyun Korean Nuclear Society 1993 Nuclear Engineering and Technology Vol.25 No.3

By making use of the microprocessor technology, instrumentation system becomes intelligent. In this study a programmable smart transmitter is designed and applied to the nuclear engineering measurements. In order to apply the smart transmitter technology to nuclear engineering measurements, the digital time delay compensation function and water level change detection function are developed and applied in this work. The time compensation function compensates effectively the time delay of the measured signal, but it is found that the characteristics of the compensation function should be considered through its application. It is also found that the water level change detection function reduces the detection time to about 7 seconds by the signal processing which has the time constant of over 250 seconds and which has the heavy noise.

FAULT-TREE-BASED RISK ASSESSMENT FOR DYNAMIC CONDITION CHANGES

Kang, Hyun-Gook,Jang, Seung-Cheol Korean Nuclear Society 2007 Nuclear Engineering and Technology Vol.39 No.2

In order to apply a static fault-tree (FT) method to a system or a plant whose configuration changes dynamically, condition gates and a post processing method are used to effectively accommodate these changes. An operator's performance change, which can be caused by these configuration changes, should also be considered to assess the risk to a plant in a more realistic manner. This study aims to develop an integrated framework to accommodate various configuration changes and their effect on an operator’s performance by using the FT model. We applied a condition-based human reliability assessment (CBHRA) method to consider various conditions endured by an operator. That is, we integrated the CBHRA method with the conventional post processing method for modeling the system configuration changes. The effect of the condition monitoring systems installed in a plant is also considered. In this study, we show an example application of the integrated framework to a probabilistic safety assessment for the shutdown phase of a nuclear power plant.

ATWS Frequency Quantification Focusing on Digital I&C Failures

Kang Hyun Gook,Jang Seung-Cheol,Lim Ho-Gon Korean Nuclear Society 2004 Nuclear Engineering and Technology Vol.36 No.2

The multi-tasking feature of digital I&C equipment could increase risk concentration because the I&C equipment affects the actuation of the safety functions in several ways. Anticipated Transient without Scram (ATWS) is a typical case of safety function failure in nuclear power plants. In a conventional analysis, mechanical failures are treated as the main contributors of the ATWS. This paper quantitatively presents the probability of the ATWS based on a fault tree analysis of a Korea Standard Nuclear Power Plant is also presented. An analysis of the digital equipment in the digital plant protection system. The results show that the digital system severely affects the ATWS frequency. We also present the results of a sensitivity study, which show the effects of the important factors, and discuss the dependency between human operator failure and digital equipment failure.

시계열 예측 모델을 이용한 커뮤니티 변화에 대한 예측

강현국(Hyun-Gook Kang),나원준(Won-Jun Nah),쿠마 아비쉑(Abhishek Kumar),이재길(Jae-Gil Lee) 한국정보과학회 2015 한국정보과학회 학술발표논문집 Vol.2015 No.6