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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
국제핵융합실험로(ITER)가 2019년까지 7개국의 공동개발사업으로 건설될 예정이다. ITER의 핵융합연료주기는 핵 융합진공용기, 삼중수소 플랜트, 연료공급부로 구성되어 있다. 이중에서 삼중수소 플랜트는 핵융합연료주기를 위한 중 수소와 삼중수소의 저장, 공급, 분리, 제거, 회수 등의 기능을 제공한다. 삼중수소 플랜트는 외부에서 중수소와 삼중수소를 공급받아 저장·공급하는 SDS, 토카막배출처리의 TEP, 수소동위원소 분리의 ISS, 삼중수소수 및 대기 처리의 WDS·ADS, 정성·정량분석의 ANS 등으로 구성된다. 이 논문에서는 삼중수소 플랜트를 구성하는 주요 공정에 대한 기 능 및 설계요건을 기술하였다. 한국은 SDS 개발에 참여하고 있으며 월성원전 삼중수소 제거설비(WTRF) 건설 및 운전경험을 통해 WDS 대한 기술을 일부 확보하였다. 향후 ISS 및 TEP에 대한 기술확보를 위한 여러 분야에서의 참여 확대를 기대하고 있다. 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.
송규민(Song, Kyu-Min),조철호(Cho, Chol-Ho),정경태(Jung, Kyung-Tae),이흥재(Lie, Heung-Jae) 한국해안해양공학회 2010 한국해안해양공학회 논문집 Vol.22 No.6
전 세계적으로 환경, 해양, 기상, 기후, 해상 및 재난예방을 지원하기 위한 해수면 조사를 위하여 해양레이더를 운용하고 있으며, 국내에서도 해양유출유와 방조제 유출수 조사 및 해상안전사고 예방을 위하여 13, 25, 42 MHz 대역의 레이더를 6개 지역에서 운용하고 있다. 그러나 측정단파대역을 이용하는 해양레이더는 실험국으로 허가받아 관리되어지고 있으며, 오늘날 주파수 분배가 논의 되고 있다. 해양레이더 주파수 분배를 위한 조사에 의하면 3~50 MHz의 국내 전파환경은 20 MHz 이상의 대역에서 레이더운용에 문제가 없으나 13 MHz를 제외한 20 MHz 이하대역은 사용검토가 필요하다. 국내 사용자는 해양레이더의 운용과 자료처리 기법에 국내의 주파수 환경을 충분히 고려해야 한다. There is increasing interest, on the global basis, in the operation of ocean surface radars for measurement of coastal sea surface conditions to support environmental, oceanographic, meteorological, climatological, maritime and disaster mitigation operations. In south Korea, ocean surface radars are operating to monitoring oil spill, outflow from dike or preventing from safety-accidents in the 6 regions (16 radial sites) by main frequency about 13, 25 and 42 MHz until the present. However, that ocean surface radars have been operated on an experimental spectrum basis. In the results of 3~50 MHz band domestic analysis to improve the regulatory status of the spectrum used by oceanographic radars, it was demonstrated that sufficient frequency bands are available for oceanographic radars on the frequency band above 20 MHz. It is difficult to deploy and operate oceanographic radars in the sub-bands below 20 MHz except for 13 MHz band. For using HF ocean surface radars one should understand the spectrum environment in Korea and should prepare a suitable operating system and data processing techniques.
송규민 ( Kyu Min Song ),윤세훈 ( Sei Hun Yun ),정흥석 ( Hong Suk Chung ),장민호 ( Min Ho Chang ),강현구 ( Hyun Goo Kang ),조승연 ( Seung Yen Cho ),구대서 ( Dae Seo Koo ),정도연 ( Do Yeon Jeong ),정동유 ( Dong You Jung ) 한국공업화학회 2010 응용화학 Vol.14 No.1
A rectangular type-bed of tritium storage was designed, fabricated and inspected. The storage bed was fabricated by brazing the tray plate, heater tube and helium loop. Brazing enables improved heat transfer for heating and cooling the plates. Feed through connections of the heater line and thermocouple line of the primary vessel enable the prevention of tritium leakage into the secondary vessel. The circumferential thermal reflectors and circular plate-type thermal reflectors for the primary vessel were fabricated to reduce heat transfer from the primary vessel to the secondary vessel, and thermal loss. Vacuum & leak inspections on the primary & secondary vessels for the fabricated rectangular tray-type bed were performed. These results were proved to have no leaks on the tubes of the primary & secondary vessels.
김경숙,손순환,송규민,한주희,한기도,도승회,Kim, Kyeong-Sook,Son, Soon-Hwan,Song, Kyu-Min,Han, Joo-Hee,Han, Kee-Do,Do, Seung-Hoe 한국방사성폐기물학회 2009 방사성폐기물학회지 Vol.7 No.3
The spent cationic exchange resins and anionic exchange resins were separated from mixed spent exchange resins by a fluidized bed gravimetric separator. The separated resins were identified by an elemental analysis and thermogravimetric analysis. The each test sample was prepared by diluting the slurry made by wet ball milling the cationic exchange resins and the anionic exchange resins separated as a spherical granular form for 24 hours. The resulting test samples showed a slurry form of less than $75{\mu}m$ of particle size and 25,000ppm of $COD_{cr}$. The decomposition conditions of each test samples from a thermal power plant were obtained with a lab-scale(reactor volume : 220mL) supercritical water oxidation(SCWO) facility. Then pilot plant(reactor volume : 24 L) tests were performed with the test samples from a thermal power plant and a nuclear power plant successively. Based on the optimal decomposition conditions and the operation experiences by lab-scale facility and the pilot plant, a commercial plant(capacity : 150kg/h) can be installed in a nuclear power plant was designed.
원자력등급 ESF 공기정화계통 시뮬레이터 제작 및 활용에 관한 연구
이숙경,김광신,손순환,송규민,이계우,박정서,홍순준,강선행,Lee, Sook-Kyung,Kim, Kwang-Sin,Sohn, Soon-Hwan,Song, Kyu-Min,Lee, Kei-Woo,Park, Jeong-Seo,Hong, Soon-Joon,Kang, Sun-Haeng 한국방사성폐기물학회 2010 방사성폐기물학회지 Vol.8 No.4
A nuclear plant ESF ACS simulator was designed, built, and verified to perform experiment related to ESF ACS of nuclear power plants. The dimension of 3D CAD model was based on drawings of the main control room(MCR) of Yonggwang units 5 and 6. The CFD analysis was performed based on the measurement of the actual flow rate of ESF ACS. The air flowing in ACS was assumed to have $30^{\circ}C$ and uniform flow. The flow rate across the HEPA filter was estimated to be 1.83 m/s based on the MCR ACS flow rate of 12,986 CFM and HEPA filter area of 9 filters having effective area of $610{\times}610mm^2$ each. When MCR ACS was modeled, air flow blocking filter frames were considered for better simulation of the real ACS. In CFD analysis, the air flow rate in the lower part of the active carbon adsorber was simulated separately at higher than 7 m/s to reflect the measured value of 8 m/s. Through the CFD analyses of the ACSes of fuel building emergency ventilation system, emergency core cooling system equipment room ventilation cleanup system, it was confirmed that all three EFS ACSes can be simulated by controlling the flow rate of the simulator. After the CFD analysis, the simulator was built in nuclear grade and its reliability was verified through air flow distribution tests before it was used in main tests. The verification result showed that distribution of the internal flow was uniform except near the filter frames when medium filter was installed. The simulator was used in the tests to confirm the revised contents in Reg. Guide 1.52 (Rev. 3).
제주해협 HFR 자료의 유효 범위 산정과 M<sub>2</sub> 조류 특성 분석
오경희,이석,박준성,송규민,정다운,Oh, Kyung-Hee,Lee, Seok,Park, Joonseong,Song, Kyu-Min,Jung, Dawoon 한국해양과학기술원 2020 Ocean and Polar Research Vol.42 No.2
The effective range of surface current data observed by high-frequency radar (HFR) operated in the northern coastal area of Jeju Island by Korea Institute of Ocean Science and Technology was estimated and the distribution and variability of the M<sub>2</sub> tidal current of the Jeju Strait was analyzed. To evaluate the HFR data, the M<sub>2</sub> tidal current corrected from 25 hours current data observed by the Korea Hydrographic and Oceanographic Agency (KHOA) was compared with the M<sub>2</sub> tidal current in the Jeju Strait analyzed from the surface currents of HFR. The reliability of HFR data was confirmed by analyzing the characteristics of the tide components of these two data sets, and the effective range of HFR data was estimated through temporal and spatial analysis. The observation periods of HFR used in the analysis were from 2012 to 2014, and it was confirmed that there is a difference in the effective range of HFR data according to the observation time. During the analysis periods, the difference between the M<sub>2</sub> current ellipses from the data of KHOA and the HFR was greater in the eastern than in the western part of the Jeju Strait, and represented a high reliability in the western and central parts of the Jeju Strait. The tidal current of the Jeju Strait analyzed using the HFR data revealed a seasonal variability a relatively weak in summer and a strong in winter, about a 17% fluctuations between the summer and winter based on the length of the semi-major axis of tidal ellipse. Appraisals and results of regarding the characteristics and seasonal variability of the M<sub>2</sub> tidal current in the Jeju Strait using HFR data have not been previously reported, so the results of this study are considered meaningful.
Reg. Guide 1.52(Rev.3)를 적용한 원전 ESF 공기정화계통 성능시험법 개선 연구
이숙경,김광신,손순환,송규민,이계우,박정서,조병호,유병재,홍순준,강선행,Lee, Sook-Kyung,Kim, Kwang-Sin,Sohn, Soon-Hwan,Song, Kyu-Min,Lee, Kae-Woo,Park, Jeong-Seo,Cho, Byoung-Ho,Yoo, Byeang-Jea,Hong, Soon-Joon,Kang, Sun-Haeng 한국방사성폐기물학회 2010 방사성폐기물학회지 Vol.8 No.4
U. S. NRC Regulation Guide 1.52 regulating ESF ACS in nuclear power plants has been revised to revision 3. To apply reduction of operability test time, allowance of alternative challenge agents for in-place leak test of HEPA filters, and upgrade of Methyl Iodide penetration acceptance criterion in activated carbon performance test suggested in Reg. Guide 1.52(Rev.3) on Yonggwang units 5 and 6 ESF ACSes, technical feasibility study was carried out with on-site experiments as well as experiments with a lab-scale model. It was confirmed that the moisture in the system returned to the level before the test in 1 or 4 days even though the moisture was removed during the operability test lasting more than 10 hours. Therefore, it is appropriate to perform monthly operability test in 15 minutes just long enough to check the operability of equipment. To change challenge material for in-place HEPA filter leak test, size of aerosol, production rate, and leak detection capability were compared for DOP and PAO. It was concluded that PAO can be substituted for DOP in nuclear power plants. The upgrade of Methyl Iodide penetration acceptance criterion from 0.175 % to 0.5 % in active carbon filter bed deeper than 4 inches was to conform to the change of activated carbon performance test method to ASTM D3803(1989). It was confirmed that Methyl Iodide penetration acceptance criterion of 0.5 % under $30^{\circ}C$, relative humidity 95 % condition was conservatively good enough for testing performance of active carbon insitu. The licence change of Yonggwang units 5 and 6 has been completed based on this study.