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Application of MARSSIM for Final Status Survey of the Decommissioning Project
홍상범,이기원,박진호,정운수,Hong, Sang-Bum,Lee, Ki-Won,Park, Jin-Ho,Chung, Un-Soo Korean Radioactive Waste Society 2011 방사성폐기물학회지 Vol.9 No.2
해체의 최종단계는 대상 부지 및 건물을 규제로부터 제외하는 것이다. MARSSIM은 부지를 개방하기 위한 최종현황조사를 수행함에 있어 요구되는 자료의 수집 등의 다양한 요건을 만족키기 위한 총괄적인 지침을 제공한다. 연구로 해체 후 부지 및 건물의 최종현황조사를 위해 MARSSIM에서 제시하고 있는 방법을 적용하였다. 연구로 부지의 특성을 반영한 개방기준을 도출하기 위해 RESRAD 및 RESRAD-Build 전산코드를 이용하여 부지 및 건물에 대해서 계산하였다. 부지 및 건물의 조사설계(Survey Design)를 위해서 잠재적 오염도 및 측정 결과를 활용하여 조사구역을 구분하였고, 개략조사 및 특성조사를 통해 수집된 다양한 결과에 기초하여 통계학적 검사를 통해 조사구역 별로 요구되는 시료의 수를 산정하게 된다. 측정된 결과에 기초하여 연구로 최종 개방기준에 만족하는 것으로 평가되었다. The release of a site and building from regulatory control is the final stage of the decommissioning process. The MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual) provides overall framework for conducting data collection for a final status survey to demonstrate compliance with site closure requirements. The KAERI carried out establishing a final status survey by using the guidance provided in the MARSSIM for of a site and building of the Korea Research Reactor. The release criteria for a site and building were set up based on these results of the site specific release levels which were calculated by using RESRAD and RESRAD-Build codes. The survey design for a site and building was classified by using the survey dataset and potential contamination. The number of samples in each survey unit was calculated by through a statistical test using the collected data from a scoping and characterization survey. The results of the final status survey were satisfied the release criteria based on an evaluation of the measured data.
연구로 2호기 수조 콘크리트의 $^3H$ 및 $^{14}C$ 공간분포
홍상범,김희령,정근호,강문자,정경환,정운수,박진호,Hong, Sang-Bum,Kim, Hee-Reyoung,Chung, Kun-Ho,Kang, Mun-Ja,Jeong, Gyeong-Hwan,Chung, Un-Soo,Park, Jin-Ho 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.4
The depth distributions of total $^3H$ and $^{14}C$ activities were characterized for the activated shielding concrete from a decommissioning of KRR-2 using the commercially available tube furnace and a liquid scintillation counter. The correlation of measurement results between $^3H,\;^{14}C$ and gammer emitter was evaluated to apply for estimating radionuclide inventory of the concrete waste generated from decommissioning KRR-2. The detection limits for $^3H$ and $^{14}C$ are 0.048 and 0.028 Bq/g respectively. The specific activities of the $^3H$ and $^{14}C$ tend to decrease exponentially as the depth of the concrete becomes deeper from the surface. In addition, the $^3H$ and $^{14}C$ activities were in good correlation with the $^{60}CO$ activities analysed for the shielding concrete of KRR-2.
김계남,정윤호,이정준,문제권,정종헌,정운수,Kim, Gye-Nam,Jung, Yun-Ho,Lee, Jung-Joon,Moon, Jei-Kwon,Jung, Chong-Hun,Chung, Un-Soo 한국방사성폐기물학회 2008 방사성폐기물학회지 Vol.6 No.1
This study examined the effect of an electrokinetic-flushing remediation for a soil of a high permeability. The soil was sampled from the site around a research atomic reactor which had high hydro-conductivities due to a high content of sand in the soil. The flow rate of the washing reagent was fast at the beginning but it was reduced as time lapsed. In the case of using citric acid as a washing reagent, the flow rate was fastest, 78.7 ml/day. The removal efficiencies of $Co^{2+}$ and $Cs^+$ from a soil cell with acetic acid were the highest, which were 95.2% and 84.2% respectively. The soil waste-solution volume generated from the electrokinetic remediation was reduced to about 1/20 of that from the soil washing remediation. Meanwhile, the electrokinetic-flushing method enhanced the removal efficiencies of $Co^{2+}$ and $Cs^+$ from the soil by about 6% and 2% respectively, compared to those by the electrokinetic method. Consequently, it was found that the electrokinetic-flushing method was more effective for the remediation of a soil with a high permeability.
박승국 ( Seung-kook Park ),지연희 ( Yeon-hee Ji ),박진호 ( Jin-ho Park ),정운수 ( Un-soo Chung ) 한국정보처리학회 2010 한국정보처리학회 학술대회논문집 Vol.17 No.1
원자력시설의 해체사업은 국내에서는 최초로 수행된 사업이다. 해체사업 활동에서 발생되는 해체 정보 및 자료의 관리와 사업의 수행을 위해 해체 정보관리 시스템 (DECOMMIS)을 개발하였다. DECOMMIS를 이용하여 해체 작업 활동, 해체 폐기물 관리, 해체 방사선 안전관리 및 품질 관리에 관한 정보/자료를 입력, 처리, 관리하고 필요 시 출력하여 활용하였다.
박승국(Seung-Kook Park),지연희(Yeon-Hee Ji),박진호(Jin-Ho Park),정운수(Un-Soo Chung) 한국정보기술학회 2010 Proceedings of KIIT Conference Vol.2010 No.-
원자력시설의 해체사업은 국내에서는 최초로 수행된 사업이다. 해체사업 활동에서 발생되는 해체 정보 및 자료의 관리와 사업의 수행을 위해 해체 정보관리 시스템 (DECOMMIS)을 개발하였다. DECOMMIS를 이용하여 해체 작업 활동, 해체 폐기물 관리, 해체 방사선 안전관리 및 품질 관리에 관한 정보/자료를 입력, 처리, 관리하고 필요 시 출력하여 활용하였다. At the Korea Atomic Energy Research Institute (KAERI), two research reactors (KRR-1 and KRR-2) and one uranium conversion plant (UCP) were decommission. A project was launched in 1997, for the decommissioning of these reactors with the goal of a completion by 2008. Another project for the decommissioning of the UCP was launched in 2001. The physical dismantling works were started in August 2003 and the entire project was completed by the end of 2009. KAERI has developed a computer information system, named DECOMMIS, for a project management with an increased effectiveness for decommissioning projects and for a record keeping for the future decommissioning projects. This decommissioning information system is consists of three sub-systems; code management system, data input system (DDIS) and data processing and output system (DDPS). The DECOMMIS was applied to the decommissioning projects of the KRR and the UCP, and was utilized to give information to the staff for making decisions regarding the progress of the projects. It is also to prepare the reference data for the R&D program which is for the development of the engineering system tools and to maintain the decommissioning data for the next projects. In this paper, the overall system will be explained and the several examples of its utilization, focused on a waste management and a manpower control, will be introduced..
해체대상 원자력시설 특성관리 DB 시스템(DEFACS)
지연희(Ji yeon hee),박승국(Park seung kook),정운수(Chung un soo) 한국정보과학회 2010 한국정보과학회 학술발표논문집 Vol.37 No.2C
원자력시설의 해체 계획을 수립하는데 해체 대상 시설의 성격을 조사하고 파악하는 것은 매우 중요하다. 해체 대상 원자력시설의 특성자료 조사 결과는 해체 페기물의 양을 예측하고, 해체 사업의 비용 산정에 크게 활용이 된다. 이를 목적으로 해체사업 대상 시설의 특성자료를 관리하는 컴퓨터 시스템인 해체시설 특성 관리시스템, DEFACS (DEcommissioning FAcility Characterization DB System)를 개발하였다.