http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
감마핵종 In-Situ 측정 연구 동향 분석 및 방사능 측정 효율 민감도 평가
라현준,김혁재,이성연,곽민우,김광표 (사)한국방사선산업학회 2023 방사선산업학회지 Vol.17 No.1
Since a large amount of radioactive waste is expected to be generated due to permanentshutdown of many nuclear power plants, it is necessary to prepare efficient management methods forradioactive waste. Therefore, there is a need for a based study to apply the In-Situ gamma spectrometry,which can simplify the measurement procedure. The purpose of this study is to analyze research casesof In-Situ gamma spectrometry and to analyze the sensitivity of measurement according to influencingfactors on In-Situ gamma spectrometry. Research cases of five institutions, including the CERN and theImperial College Reactor Centre (ICRC), were selected as the institutions to be investigated. Researchon the In-Situ gamma spectrometry was conducted on the satisfaction of the acceptance criteria forradioactive waste and the analysis of residual radioactivity in the site. In-Situ Objective Counting System(ISOCS) was used as a major measuring device. Sampling and computer code were used to verify theanalysis results. For evaluation of measuring sensitivity according to influencing factors on In-Situgamma spectrometry, the thickness of the measurement target, the distance between the detector andthe target, the angle of the collimator, and the contamination location were performed using ISOCS’sGeometry Composer. In every case, based on 122 keV, the efficiency decreased as the energy increased inthe high energy region, and the efficiency decreased as the energy decreased in the low energy region. Asthe target thickness increased, the efficiency decreased, and as the distance between target and detectorincreased, the efficiency decreased. As the distance between contamination and detector increased, theefficiency decreased, and as the angle of the collimator increased, the measurement efficiency increased. However, when simulating the measurement situation using Geometry Composer, the background is notconsidered, and the probability of incident in the background increases as the angle increases, so furtherresearch needs to be conducted in consideration of these. This study can be utilized when applying the In-Situ gamma spectrometry of radioactive waste clearance in the future.
국내 · 외 사용후핵연료 저장 및 최종관리 정책 현황 분석
라현준,김혁재,김기훈,남형우,김광표 (사)한국방사선산업학회 2021 방사선산업학회지 Vol.15 No.4
Currently, as the saturation of the temporary storage facility for spent fuel in nuclearpower plants is imminent in Korea, it is necessary to prepare additional management. Therefore,it is necessary to investigate the status of domestic and foreign spent fuel management so that anappropriate spent fuel management can be prepared in the future. The objective of this study is toinvestigate and analyze the status of domestic and foreign spent fuel storage and final managementpolicies. Seven countries, including the United States (US), United Kingdom (UK), and Korea wereselected as the target countries. Among spent fuel storage status, the amount of domesticspent fuel storage was found to be 1.5 times of the overseas average (except US). As for thecurrent status of spent fuel storage facilities, spent fuel after temporary storage is stored in ISFSI(Independent Spent Fuel Storage Installation), interim storage facility, and reprocessing facilitystorage pool abroad. In Korea, since there is no interim storage facility, the spent fuel is stored in theon-site storage facility. In the case of storage methods, both wet and dry storage methods are usedin the US, UK, Japan, and Korea. In the case of regulatory and disposal management agenciesamong the final management policies, each country operates separated regulatory and disposalmanagement agencies. As for the status of adoption of the final management policy, the US,Sweden, and Finland adopt direct disposal as the final management policy for spent fuel. In theFrance and Japan, reprocessing is adopted as a final management policy. In the UK, reprocessinghas been adopted as a final management policy, but will be abandoned. The US, Sweden, andFinland, which have adopted direct disposal as their final management policy, have completed thesite selection for the repository. Among the France, and Japan, where reprocessing is adopted as afinal management policy, the site selection for a high-level radioactive waste disposal site has beencompleted in France. Also, in the UK and Japan, the site selection for a repository is in progress. The results of this study can be utilized when preparing a management spent fuel in the future.