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원자력발전소 해체 방사성폐기물 특성보고서 작성 방안 제안
김창락,이선기,김헌,박해수,성석현,공창식,Kim, Chang Lak,Lee, Sun Kee,Kim, Heon,Park, Hae Soo,Sung, Suk Hyun,Kong, Chang Sig 한국시스템엔지니어링학회 2021 시스템엔지니어링학술지 Vol.17 No.1
Radioactive waste generated from nuclear power plant decommissioning shall be strictly managed so that radioactive materials above the allowable limit are not leaked into the environment. Radioactive wastes shall be classified and treated for management based on characteristics such as the type of waste, physicochemical properties, nuclide concentration and radioactivity. Waste characterization report shall be prepared and submitted to the disposal facility operator to ensure that the treated waste is suitable for disposal. The disposal facility operator shall review the waste Characterization report and visit the nuclear power plant decommissioning site to ensure that the wastes are processed step by step according to the plan. The waste Characterization report may be used as input data to evaluate disposal facility safety. Domestic and foreign data are collected and reviewed to confirm the entire processes from waste generation to delivery. This paper proposes the method to prepare the waste Characterization report which contains data and information on waste characteristics, treatment facilities & method and packaging method & container.
원자력발전소 해체 방사성폐기물 처분 적합성 검증을 위한 인수기준 이행 흐름도 개발
김창락,이선기,김헌,성석현,박해수,공창식,Kim, Chang Lak,Lee, Sun Kee,Kim, Heon,Sung, Suk Hyun,Park, Hae Soo,Kong, Chang Sig 한국시스템엔지니어링학회 2021 시스템엔지니어링학술지 Vol.17 No.1
When the decommissioning of South Korea nuclear power plants is promoted in earnest with the permanent shutdown of Kori Unit 1 in 2017, a large amount of various types of radioactive waste will be generated. For minimal generation and safe management of decommissioning waste, the waste should be made by appropriate classification of the dismantling waste characteristics in accordance with physical, chemical and radiological characteristics to meet the acceptance criteria of disposal facilities. Replacing the preliminary inspection at the site for the compliance of the waste acceptance criteria (WAC) of medium and low-level radioactive waste with the generator's own radioactive waste certification program (WCP), from the perspective of disposal, the optimization of waste management at the national level contributes to the efficient availability of disposal, such as the processing of non-conforming radioactive wastes at the site. To this end, it is important to evaluate radioactivity in each system and area such as nuclear reactors before decommissioning is carried out in earnest, and the prior removal of harmful wastes is important. From waste collection to waste disposal, decommissioning waste should be managed at each stage in consideration of the acceptance criteria of disposal facilities to minimize the generation of non-conforming waste.
이병관,김창락,이선기,김헌,성석현,박해수,공창식,Lee, Byeong Gwan,Kim, Chang Lak,Lee, Sun Kee,Kim, Heon,Sung, Suk Hyun,Park, Hae Soo,Kong, Chang Sig 한국시스템엔지니어링학회 2021 시스템엔지니어링학술지 Vol.17 No.1
Radioactive mixed waste (RMW) means waste mixed with radioactive substances and hazardous substances. In Korea, there are definitions and disposal restrictions on RMW in the Nuclear Safety Management Act, but it is difficult to apply because the contents are insufficient, so this paper proposed applicable management standards. The main RMW generated from nuclear power plants is waste oil, waste asbestos, PCB, and waste fluorescent liquid, and their radiation characteristics are mostly at very low levels and some are estimated at low levels. In addition to nuclear power plants, RMW also occurs in research institutes, industries, and hospitals. The acceptance criteria of all disposal facilities in the world basically prohibit disposal of RMW unless the hazardous substances of RMW are removed or mitigated below the standard value. Cases in Korea, the United States, Japan and Europe were reviewed to propose the RMW management standards in Korea. With reference to the results of the above review, this paper clearly defined RMW and proposed detailed management standards for the separation, storage, treatment and disposal of hazardous substances by applying the Waste Control Act. It also mentioned legislation of management standards, regulatory methods, and acceptance criteria of disposal facility operator.
역사시대 고분을 이용한 중저준위 방사성폐기물의 천층처분 덮개성능 자연유사연구
박진백,박주완,김창락,양시은,이선복,Park Jin-Beak,Park Joo Wan,Kim Chang-Lak,Yang Si Eun,Lee Sun Bok 한국방사성폐기물학회 2005 방사성폐기물학회지 Vol.3 No.4
중저준위 방사성폐기물 천층처분시설의 처분덮개설계 및 성능평가를 위해 국내 역사시대 고분연구를 수행하였다. 처분덮개 성능과 관련된 국내외 연구현황을 조사하고 삼국시대 고분을 중심으로 봉분의 층상특성을 정리하였다. 국내 고분에 대한 봉토의 시료채취와 시료에 대한 수리전도도 측정 및 분석을 실시하였다. 고분에 대한 자연유사 연구에서 발굴조사보고서 상에 제시된 봉토의 유사판축기법의 적용, 모세관 방벽현상과 배수로를 이용한 봉분 내 습도조절 여부를 천층처분 시설설계에 활용할 수 있을 것으로 판단된다. 향후 국내 고분발굴현장이 있을 때 현장을 방문하여 필요한 자료수집과 더불어 원자력분야의 관심사와 필요사항에 대하여 국내 고고학계와의 정보교환이 이루어져야 할 것으로 판단된다.
미키다디 살레히,김창락,Salehe, Mikidadi,Kim, Chang-Lak Korean Radioactive Waste Society 2013 방사성폐기물학회지 Vol.11 No.4
Borehole Disposal Concept (BDC) was initiated by the South African Nuclear Energy Corporation (NECSA) with the view to improve the radioactive waste management practices in Africa. At a time when geological disposal of radioactive waste is being considered, the need to protect ground water from possible radioactive contamination and the investigation of radionuclides migration through soil and rocks of zone of aeration into ground water has becomes very imperative. This is why the Borehole Disposal Concept (BDC) is being suggested to address the problem. The concept involves the conditioning and emplacement of disused sealed radioactive sources in an engineered facility of a relatively narrow diameter borehole (260 mm). Tanzania is operating a Radioactive Waste Management Facility where a number of spent sealed radioactive sources with long and short half lives are stored. The activity of spent sealed radioactive sources range from (1E-6 to 8.8E+3 Ci). However, the long term disposal solution is still a problem. This study therefore proposing the country to adopt the BDC, since the repository requires limited land area and has a low probability of human intrusion due to the small footprint of the borehole.
이상호,서형우,김창락,Lee, Sang-Ho,Seo, Hyung-Woo,Kim, Chang-Lak Korean Radioactive Waste Society 2018 방사성폐기물학회지 Vol.16 No.1
Kori unit 1, the oldest commercial nuclear power plant in South Korea, was permanently shut down in June 2017. There are a lot of things to consider in decommissioning nuclear power plants, and one of them is the radiological environmental impact assessment. Performed to promote the health and safety of residents around the nuclear power plant, radiological environmental impact assessment aims to confirm that off-site radiological dose from radioactive material released from the facility does not exceed the regulatory criteria. There are three main parts of environmental impact assessment: pre-decommissioning environmental monitoring, environmental monitoring during decommissioning, and impact on nearby residents. At present, although the Korea Nuclear Safety Act stipulates that radiological environmental impact assessment resulting from decommissioning should be carried out, the details have not been specified. Therefore, this paper compares and analyzes guidelines for evaluation of radiological environmental impacts of nuclear power plants overseas, and presents a draft on the assessment of radiological dose resulting from decommissioning according to the Korean situation.
부지환경종합관리시스뎀 개발용 SEMS모듈 설계에 관한 연구
고도영,박세문,김창락,Ko Do-Young,Park Se-Moon,Kim Chang-Lak 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
During the last two years, Site Information and Total Environmental database management System (SITES) ver. 1.0 has been developed for the systematic SITES Database Module (SDM), which includes site information, facility information and environmental information. The SITES includes the module for site environmental monitoring system and safety assessment (M&A) system for the nuclear facility. SITES is expected to be an effective system for the radioactive waste disposal management facility. Currently, SITES ver.2.0 is under development after the SITES ver.1.0 that is focused on the M&A system. The main purpose of this paper is to introduce and try to account for the major development in the concept of SEMS sub-module of the M&A module. The SEMS is purposed of development of the program for real time environmental monitoring, prediction, and automatic alarm system using SITES Database and related information.
윤정현,박주완,주민수,김창락,박진백,Yoon, Jeong-Hyoun,Park, Joo-Wan,Ju, Min-Su,Kim, Chang-Lak,Park, Jin-Baek 한국방사성폐기물학회 2008 방사성폐기물학회지 Vol.6 No.1
A new proposed repository has a final capacity of 800,000 drums radioactive waste. Most of foreign repositories have a general practice of segregating control zones which mainly contributes to classification of degree of control, whether it is called buffer zone or not. Domestic regulatory requirements of establishment of buffer zone in a repository are not much different from those of nuclear power plants for operation period, in which satisfactory design objective or performance objective is the most important factor in determination of the buffer zone. The meaning of buffer zone after closure is a minimum requested area which can prevent inadvertant intruders from leading to non-allowable exposure during institutional control period. Safety assessment with drinking well scenario giving rise to the highest probability of exposure among the intruder's actions can verify fulfillment of the buffer zone which is determined by operational safety of the repository. At present. for the repository to be constructed in a few years, the same procedure and concept as described in this paper are applied that can satisfy regulatory requirements and radiological safety as well. However, the capacity of the repository will be stepwise extended upto 800,000 drums, consequently its layout will be varied too. Timely considerations will be necessary for current boundary of the buffer zone which has been established on the basis of 100,000 drums disposal.