화자 식별과 얼굴 인식을 이용한 대규모 보안 시스템

홍승준,구자윤,권영헌,이건상 한양대학교 이학기술연구소 2000 이학기술연구지 Vol.2 No.

본 논문에서는 화자 식별과 얼굴 인식을 이용하여 대규모 보안 시스템을 개발하였다. 인식 에러를 줄이기 위해 전 처리 화자 식별기로 DHMM(Discrete hidden Markov Model)을 사용하였고, 후 처리기에서는 얼굴 인식을 위해 신경망을 사용하였다. Visual C++MFC을 사용하여 Sound Card와 Digital camera를 제어하였다. 그리고 본 논문에서 개발한 프로그램을 사용하여 실시간으로 실험하였다. 본 논문에서 인식에 사용한 특징 벡터로는 Filter bank energy, LSF와 Cepstrum coeffient이고, 얼굴 인식의 대표 벡터는 2차원 Filter bank energy를 사용하였다. 실험에서 사용된 사람은 학교에서 무작위로 83명을 선택하였다. Test를 위해 2049개의 음성 데이터와 365개의 얼굴 이미지를 사용하였다. 복합 모델로 구성한 본 시스템은 등록화자에 대해 98.8%의 Access rate와 비 등록화자의 99.82%의 deny rate을 나타내었다. In this paper, we developed the large scale security system using speaker identification and face recognition. In order to reduce the recognition error we used DHMM(Discrete Hidden Markov Model) in speaker identification for pre-processor and neural network in face recognition for post-processor. To test the on-line performance of total system we directly controlled the sound card and the digital camera in the environment of Visual C++MFC. And we developed the program to test the performance of the system in real time. We used filter bank energies, LSF and cepstrum coefficients as the feature vectors of speech, and the 2-dimensional filter bank energies extracted in the range of the representative feature on face. In experiments, we randomly selected 83 persons in school, and then chosen 10 persons as an enrolled person and 73 persons as a non-enrolled person. So we tested 2049 speech data and 365 image data. It turned out that the hybrid system would have 98.8% access rates for the enrolled persons and 99.82% deny rates for the non-enrolled persons.

온도 기울기(temperature gradient) 젤에서 Heteroduplex Analysis 기법을 이용한 돌연변이 DNA의 검출

조용석,구미자,박귀근,박영서,강종백 A.R. Liss 1998 ENVIRONMENTAL MUTAGENS AND CARCINOGENS Vol.18 No.2

초고진공용 주사형 터널링 현미경의 제작

김달현,박해원,이세경,구자용,김구영 韓國非破壞檢査學會 1994 한국비파괴검사학회지 Vol.14 No.3

진공도가 10-¹¹Torr 수준의 초고진공 상태에서 작동되고 실제공간에서 개별원자를 구별할 수 있는 주사형 터널링 현미경을 제작하였다. 주사형 터널링 현미경의 배경 및 작동원리와 제작에 있어서의 제문제점들을 서술하고 흑연결정과 실리콘에 대해서 관찰한 결과를 보고한다. A scanning tunneling microscope has been built, which can resolve atomic arrangements of conductors and semiconductors in ultra high vacuum below 10-¹¹Torr. Its background operational principles are reviewed and the guide lines in building the scanning tunneling microscope are shown. The results of measurements for highly oriented pyrolytic graphite and Si(111) surface are presented

내시경적 점막절제술로 치험한 식도 과립상 세포종 1례

강혁주,김성욱,최석진,이중현,장재식,서영범,윤병구,박건욱,김성자,김용섭,강승완,이구,양창헌,이창우,김욱년,이광헌,서정일 동국대학교 의학연구소 2000 東國醫學 Vol.7 No.-

과립상 세포종은 Schwann 세포 기원으로 생각되며 인체에 비교적 드물게 발생한다. 과립상 세포종은 전신 어느 곳에서나 발견될 수 있으나 주로 혀, 구강, 피부 혹은 유방 등에서 호발하며 드물게 위장관에서 발견된다. 위장관에서는 식도에서 가장 호발하며 다음으로 위, 대장 순이다. 과립상 세포종은 대부분, 특히 위장관에서는 양성이며 소수의 악성 병변이 보고되었다. 이러한 이유와 함께 수술 전의 진단이 어렵기 때문에 과립상 세포종에 대한 근본적인 치료는 현재까지 외과적 절제술이다. 최근에 시도되는 치료방법들로는 내시경적 레이저 치료, 용종절제술, 내시경적 점막 절제술 등이 있다. 저자들은 상부 소화관 내시경검사를 시행하여 식도 과립상 세포종을 진단하고 내시경적 점막 절제술을 시행하여 합병증 없이 퇴원하여 현재 재발없이 경과 관찰중인 1례를 경험하였기에 보고하는 바이다. Granular cell tumors, which occur infrequently, are probably of Schwann cell origin. They can occur almost anywhere in the body but usually affect the tongue, oral cavity, skin, or breasts and are rarely found in the gastrointestinal tracts. The esophagus is the most frequent gastrointestinal site, followed by the stomach and the colon. Granular cell tumors are generally benign, especially in the gastrointestinal tract, some malignant lesions have been reported. For this reason, and also because preoperative diagnosis is difficult, the standard treatment for granular cell tumor has until now been surgical excision. In recent years, other therapeutic methods is endoscopic laser therapy (ELT), polypectiomy, endoscopic mucosal resection (EMR). We report a case of esophageal granular cell tumor which was diagnosed by an endoscopy and managed using an endoscopic mucosal resection without complication.

Montmorillonite Alteration in Alkaline and Saline Solutions and Its Retention Capacity for Cesium and Iodide

Ja-Young Goo,Bong-Ju Kim,Jang-Soon Kwon,Ho Young Jo 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1

Bentonite is a potential buffer material of multi-barrier systems in high-level radioactive wastes repository. Montmorillonite, the main constituent of the bentonite, is 2:1 type aluminosilicate clay mineral with high swelling capacity and low permeability. Montmorillonite alteration under alkaline and saline conditions may affect the physico-chemical properties of the bentonite buffer. In this study, montmorillonite alteration by interaction with synthetic alkaline and saline solution and its retention capacity for cesium and iodide were investigated. The experiments were performed in three different batches (Milli-Q water, alkaline water, and saline water) doped with cesium and iodide for 7 days. Alteration characteristics and nuclide retention capacity of original- and reacted bentonite was analyzed by X-ray diffraction (XRD), Fourier Transform Infrared (FTIR) spectroscopy, Scanning Electron Microscope (SEM), Nuclear Magnetic Resonance (NMR) and Cation Exchange Capacity (CEC) analysis. From the results, cesium retention occurred differently depending on the presence of competing ions such as K, Na, and Mg ions in synthetic solutions, while iodide was negligibly removed by bentonite. Montmorillonite alteration mainly occurred as cation exchange and zeolite minerals such as merlinoite and mordenite were new-formed during alkaline alteration of the montmorillonite. CEC value of reacted bentonite increased by formation of the zeolite minerals under alkaline conditions.

Leaching Behaviors of Cs (Ⅰ), Sr (Ⅱ), Co (Ⅱ), and Eu (Ⅱ) From Solidified Portland Cement Matrix

Ja-Young Goo,Bong-Ju Kim,Jongtae Jeong,Jang-Soon Kwon 한국방사성폐기물학회 2021 한국방사성폐기물학회 학술논문요약집 Vol.2021 No.06

A Review on Effects of Hyper-alkaline Alteration of Buffer on Migration of Radionuclides Under Repository Conditions

Ja-Young Goo,Ho Young Jo,Jang-Soon Kwon 한국방사성폐기물학회 2021 한국방사성폐기물학회 학술논문요약집 Vol.2021 No.11

Effects of EDTA on Leaching Behaviors of Co(II) and Cs(I) Immobilized in Cement Specimen

Ja-Young Goo,Seonggyu Choi,Bong-Ju Kim,Ki Jong Jang,Jongtae Jeong,Jang-Soon Kwon 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.1

Numerous low-and intermediate level radioactive wastes were generated from the decommissioning processes of nuclear power plants. Radionuclides such as Co and Cs contained in decommissioning wastes should be immobilized to prevent the release of radionuclides from the wastes due to its harmful impacts on ecosystem by high radioactivity and long half-life. Ethylenediaminetetraacetic acid (EDTA) used as decontamination agent can be contained in cement waste during decommissioning process of nuclear power plants. In addition, EDTA can be stably and strongly bound with radionuclides, resulting in the acceleration of the nuclide release from solidified cement matrix. Here, we investigated the effects of EDTA on leaching behaviors of Co and Cs immobilized in the cement specimen. The leaching tests were performed according to the ANS 16.1 “Measurement of the leachability of solidified low-level radioactive wastes by a short-term test procedure”. From the results, an increase in the EDTA content in the cement specimen led to an increase in Co leaching, whereas a decrease in Cs leaching. Leaching of Cs was dominantly controlled by diffusion from the pore space of the cement specimen to the solution. The effective diffusion coefficient and leachability index of nuclide were determined using the diffusion-release models of ANS 16.1. The results of present study can be used in the safety assessment for disposal of the radioactive waste generated by decommissioning of nuclear power plants.

An experimental concept for investigating long-term buffer behaviors considering repository conditions

Ja-Young Goo,Bong-Ju Kim,Ki Jong Jang,Ho Young Jo,Jang-Soon Kwon 대한지질학회 2021 대한지질학회 학술대회 Vol.2021 No.10

The disposal of high-level radioactive waste (HLW) in a deep geological environment has been considered by many countries as one of the safest and suitable solutions for their management. The safety of the HLW repository rely on a multi-barrier concept for retarding the migration and diffusion of nuclides. The multi-barrier system consist of the engineered barrier system which includes the waste canister, buffer, and backfill materials and natural barrier system which includes host rock and its near subsurface environment. However, long-term operation of the repository about tens or hundreds of thousands years might degrade the performance of multi-barrier system, resulting in a nuclide mobile condition. Thus, the safety evaluation of multi-barrier system under the repository condition through an experimental study is important to predict its performance in terms of operation time for the repository. The main objective of this study is to introduce the experimental concept for investigating the effects of physico-chemical alteration of multi-barrier system on fate and transport of radionuclides under repository conditions such as high pH, salinity, temperature, and pressure conditions. Initial characteristics of the buffer material such as retention capacity for radionuclides and sorption capacity expect to be changed slightly according to contact with groundwater of various compositions and thermal conditions. Also, the interaction between buffer and waste canister and between buffer and natural barrier system will be studied through the experiment. The behaviors and transport of radionuclides through the multi-barrier system are also planned to investigate, which are used for input data of the safety assessment of the repository.

Leaching Characteristics of Cs(I) and Co(II) Immobilized in Cement Waste Forms Containing EDTA

Ja-Young Goo,Seonggyu Choi,Bong-Ju Kim,Jongtae Jeong,Jang-Soon Kwon,Ho Young Jo 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

Radionuclides in low- and intermediate-level radioactive wastes from the decommissioning process of nuclear power plants were generally immobilized by cementation methods. Ethylenediaminetetraacetic acid (EDTA), which is extensively used as a decontamination agent, can affect the behaviors of radionuclides immobilized in cement waste forms. In this study, the effects of EDTA contained in simulated radioactive decommissioning wastes on the leaching characteristics of immobilized Co and Cs and the microstructure evolution of cement waste form. Co leaching was accelerated by the formation of Co–EDTA complexes with high mobility and solubility. Cs leaching was hindered by the ion competition with other metal–EDTA complexes for releasing from the cement waste form. Cs leaching was also retarded by carbonated layer at edge of the cement waste form, which process is facilitated by the presence of EDTA. Finally, the effects of EDTA on the leaching characteristics of immobilized Cs and Co and the microstructure evolution of the cement waste form should be considered to ensure the safety of disposal for lowand intermediate-level radioactive wastes.