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소장 금속유물의 과학적 보존처리-보물 제930호 및 이완장군 유품을 중심으로
문환석,정기정,김선덕,Moon, Whan-Suk,Jung Ki-Jung,Kim, Sun-Duk 국립문화재연구소 1995 保存科學硏究 Vol.16 No.-
We conserved efficiently artifacts such as Pole(Treasure No. 930)and Helmet(General of Lee, Wan:1602∼1674) which are housed in the historical department, Kyonggi-do provincial office. It were carrying out physical and chemical methods for removing corrosion products at the same time. During the treatment, the spear was proved to coat gold amalgam on the surface and the pole restored its original state as a result using X-ray fluorescence analysis and Radiography, in addition, we could find their skill and technology by examining the section painted lacquer with wooden by microscopy.
표면처리 한 polysulfone 막으로 오일/물 에멀젼의 한외여과 특성
정경환,이근우,김길정,정기정,김철,Jeong, Gyeong-Hwan,Lee, Kune-Woo,Kim, Kil-Jeong,Jung, Ki-Jung,Kim, Chul 한국에너지학회 1999 에너지공학 Vol.8 No.1
본 연구는 polysulfone 막을 표면처리 하여 오일 폐수를 한외여과 처리하였고 이때 fouling의 감소효과를 실험하였다. 고분자나 계면활성제를 polysulfone막에 흡착시켜 표면처리를 하였다. 다양하게 표면처리된 막으로 dodecane(0.1 v%)/물 에멀젼과 dodecane-계면활성제/물 에멀젼을 회분식 실험방법으로 수행하였다. SDS로 개질한 막으로 dodecane-계면활성제/물 에멀젼을 환외여과 처리하였을 때 fouling이 가장 작게 나타났고, 재사용에 좋은 방법으로 나타났다.
문환석,황진주,김선덕,강대일,정기정,정영동,Moon, Whan-Suk,Hwang, Jin-ju,Kim, Sun-Duk,Kang, Dai-Ill,Jung, Ki-Jung,Jung, Young-Dong 국립문화재연구소 1995 保存科學硏究 Vol.16 No.-
Several comparisons of treatment methods for stabilizing corroded Chinese coins at Shin-an marine sites were investigated. In aqueous solution, the seexamination were performed to show whether chloride ions are gradually removed, patination changes are acceptable and archaeological details are identified. The six desalting methods showed that the orders of removal of chloride ions were ranked electrolysis (electolyte : 0.1M sodium sesqui.)> 5% sodium dithionite(1M NaOH)> 5%sodium dithionite(0.1M sesqui.)> 5% citric acid> 0.1M sodium sesquicarbonate>deionized water. As the examinations of moisture absorption to the relative humidity has compared for bronze disease, all of desalted coins for the R.H 53% and R.H 75%except to R.H 95% are showed serious bronze disease.
진재현,박병석,고병승,윤지섭,정기정,Jin Jaehyun,Park Byungsuk,Ko Byungseung,Yoon Jisup,Jung Ki-Jung Korean Radioactive Waste Society 2005 방사성폐기물학회지 Vol.3 No.3
In this paper, a prototype of the Bridge-Transported Servo Manipulator (BTSM) system is introduced, which has been developed to do operation and maintenance jobs remotely in a hot cell. The system consists of a telescopic transporter, a slave arm, a master arm, and a control system. Several tests such as a positional tracking, a weight handling, reliability, and operability have been performed and test results are presented. Based on the test results, an upgraded system which will be used during demonstrations of the advanced spent fuel conditioning process (ACP) has been designed.
송규민 ( Kyu Min Song ),손순환 ( Soon Hwan Sohn ),정홍석 ( Hong Suk Chung ),윤세훈 ( Sei Hun Yun ),정기정 ( Ki Jung Jung ) 한국화학공학회 2012 Korean Chemical Engineering Research(HWAHAK KONGHA Vol.50 No.4
International Thermonuclear Experimental Reactor (ITER) will be constructed in 2019 according to the JIA (Joint Implementation Agreement) of 7 countries. The ITER fusion fuel cycle consists of fusion vacuum vessel, tritium plant and fuelling system. The tritium plant provides the functions of storage, delivery, separation, removal and recovery of the deuterium and tritium used as fusion fuels for the ITER. The tritium plant systems supply deuterium and tritium from external sources and treat all tritiated fluids from ITER operation through Storage and Delivery System (SDS), Tokamak Exhaust Processing (TEP), Isotope Separation System (ISS), Water Detritiation System & Atmosphere Detritiation System (WDS & ADS) and Analysis System (ANS). In this paper, the functions and design requirements of the major systems in the tritium plant and the status of R&D are described. Korean party is developing the SDS for ITER tritium plant and partially attaining the WDS technology through the construction and operation experience of the Wolsong Tritium Removal Facility (WTRF). Now it is expected that researchers in other fields such as chemical engineering take part in the development of upcoming technologies for ISS and TEP.
Treatment of Radioactive Liquid Waste Using Natural Evaporator and Resulted Exposure Dose Assessment
Jung,Ki-Jung,Kim,Eun-Han,Jeong,Gyeong-Hwan,Park,Seung-Kook,Park,Hyun-Soo 대한방사선 방어학회 1999 방사선방어학회지 Vol.24 No.2
극저준위 방사성액체폐기물 처리를 위하여 공기의 온도와 습도 및 유입 공기의 속도에 따른 증발량의 관계를 천을 이용한 강제증발실험 장치로 실험하였다. 그 결과 각각의 변수와 증발량의 상관관계를 실험식으로 도출하였다. 또한 Cs-137을 함유한 모의폐액을 사용하여 본 장치에 대한 제염계수를 얻은 결과 DF=10⁴으로 나타났다. TRIGA Mark Ⅱ & Ⅲ 연구용 원자로 폐로시 발생되는 극저준위 방사성액체폐기물을 증발장치로 처리할 때 주변의 일반개인에 대한 연간 피폭선량을 보수적으로 평가한 결과, 유효선량(effective dose)은 1.01 x 10 mSv이고, 환경으로 배출되는 공기의 방사능 농도(Cs-137)는 4.637x10 μCi/cc air 이다. 따라서 극저준위 방사성액체폐기물의 처리를 위하여 강제증발장치를 사용하는 것은 주민에 아무런 영향이 없음을 알 수 있었다. The influence of the relative humidity, the temperature and the velocity of supply air on evaporation rate has been studied with non-boiling forced evaporation system in order to treat very low level radioactive liquid wastes produced from the decontamination and decommissioning activities. Experimental data on the evaporationrate have been obtained with the divers variables and experimental equation of air velocity was also obtained by the correlation of those data. The decontamination factor of this system was also obtatined by the experimental data from a simulated liquid waste containing Cs-137 radio isotope : DF=10⁴. Since the commercial system will be operated for the treatment of the very low level radioactive liquid waste produced from decontamination & decommissioning of TRIGA Mark-Ⅱ&Ⅲ research reactor, the environmental assessment has been conducted to improve the operational safety. Exposure dose rate for an individual member of general public was assessed, and it showed that it was very lower than indivikual dose limits. The release of radioactivity of radioisotope material (Cs-137) to the environment was assessed, and result showed that it was 4.637x10 μCi/cc. .