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RISS 인기검색어
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- 저자 : 손순환 ( Soon Hwan Sohn ) (검색결과 4 건)
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고리 1발전소 부지 내 지하수 유동 및 삼중수소 이동 모델링
손욱,손순환,전철민,김구영,Sohn, Wook,Sohn, Soon-Hwan,Chon, Chul-Min,Kim, Kue-Yong 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.3
원전 운영자는 계통 및 기기의 열화 등에 의해서 발생할 수 있는 비계획적 방사성물질의 방출로 인한 환경 및 주변 주민에의 영향을 합리적으로 달성 가능한 한 낮게 유지하기 위해서 비계획적 방출을 조기에 감지할 수 있는 부지에 적합한 지하수 감시 프로그램을 수립해야 하며, 이를 위해서는 해당 부지의 수문지질 특성의 파악을 통해 지하수 유동을 평가해야 한다. 본 논문에서는 고리 1호기에서 계획되고 있는 지하수 감시 프로그램에 필요한 자료를 제공하기 위해, 고리 1발전소 부지의 기존 수문지질 조사 및 관련 자료의 조사를 통해 부지 내 지하수 유동특성을 파악하고 이를 바탕으로 가상의 비계획적 방출에 의한 삼중수소의 오염운(汚染雲)의 거동을 모의하였다. 모의 결과 지하수의 주 유동 방향은 남서방향이었으며 지하수의 대부분이 남쪽 및 동쪽 바다로 유입되었다. 삼중수소 오염운 역시 바다로 향하였으나 지하집수조(dewatering sump)에 의해 그 속도가 지연되는 것을 확인할 수 있었다. Nuclear power utilities should establish a site-specific groundwater monitoring program for early detection of unplanned radioactive material's releases which can occur due to degradation of systems, structures and components of the nuclear power plants in order to keep the impact of the unplanned releases on the environment and the residents as low as reasonably achievable. For this end, groundwater flow on site should be evaluated based on characterization of the hydrogeology of a site of concern. This paper aims to provide data necessary for establishing groundwater monitoring program which is currently considered at Kori nuclear power plant 1 by characterizing groundwater flow system on the site based on the existing hydrogeological studies and related documents, and by modeling tritium transport. The results showed that the major groundwater flow direction was south-west and that most of groundwater entered a southern and eastern seas. Although the tritium plume also released into the sea, its rate was delayed by dewatering sump.
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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).
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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.
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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.
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