• Nuclear Engineering and Technology
• /
• 제53권1호
• /
• pp.234-243
• /
• 2021

In the research or project planning for the decommissioning of a nuclear power plant, one of several preparations will be the establishment of a list of potential radionuclides to be considered at the time of characterization or final status surveys. Reliable data for selection of potential radionuclides during the transition period to prepare for decommissioning will depend heavily on historical data at the site or, where possible, sampling analysis. However, during the transition period, direct sampling can be challenging, depending on the circumstances of the site or national regulation. A methodology of selecting potential radionuclides for nuclear facility sites which largely consists of three major processes: production of initial list of radionuclides, selection of the insignificant radionuclide that will be eliminated, and consideration of site characterization or sampling. For developing a preliminary list of potential radionuclides for Kori Unit 1 decommissioning, the list of initial radionuclides was made referring to the technical documents applied at decommissioned NPPs in the U.S and additional reference materials applied until the operation of NPPs in Korea. For the screening of insignificant radionuclides, we applied criterion of less than 0.1% of the amount of radioactivity inventory and confirmed the dose fraction using the RESRAD code. The final suit of radionuclides was established, which should be supplemented by reflecting site characterization and sampling process in the future. Thus, the methodology and results for the selection of potential radionuclides suggested in this paper can give an insight as a future reference to deriving DCGLs in relation to site remediation of decommissioning nuclear plants.

• 방사성폐기물학회지
• /
• 제14권2호
• /
• pp.123-134
• /
• 2016

최근 국내에서는 월성 1호기 및 고리 1호기를 포함하여 운영 중인 원자력발전소가 노후화함에 따라 원전 해체에 대한 관심이 많이 증대되고 있다. 이와 관련하여 월성 1호기의 계속운전이 최근 결정되었으며, 고리 1호기의 경우 2017년 6월 영구정지하기로 결정되었다. 이에 본 논문에서는 상업용 원자로로서는 국내 최초로 해체가 예정된 고리 1호기에 대해, 원자로 압력용기 자체의 해체로 인해 발생하는 방사성폐기물 최종 처분량을 원자로 압력용기 절단 방법 및 방사성폐기물 처분용기를 고려하여 산정하였다. 처분용기를 고려한 방사성폐기물 처분량을 산정한 결과 원자로 압력용기 몸통 부위보다는 반구 형태의 헤드 부분을 작게 절단할수록 최종 처분량이 감소하는 것으로 예측되었다. 또한 경주 방폐장의 200 L 및 320 L 드럼 처분용 처분용기의 경우 무게 제한으로 인해 적재효율이 좋지 못한 것으로 나타났다.

• Journal of Radiation Protection and Research
• /
• 제48권1호
• /
• pp.20-27
• /
• 2023

Background: As the number of nuclear facilities nearing their pre-determined design life increases, demand is increasing for technology and infrastructure related to the decommissioning and decontamination (D&D) process. It is necessary to consider the nature of the dismantling environment constantly changing and the worker doing new tasks. A method was studied that can calculate the effect of learning and the change in work time on the work process, according to the learning-forgetting curve model (LFCM). Materials and Methods: The LFCM was analyzed, and input values and scenarios were analyzed for substitution into the D&D process of a nuclear facility. Results and Discussion: The effectiveness and efficiency of the training were analyzed. It was calculated that skilled workers can receive a 16.9% less collective radiation dose than workers with only basic training. Conclusion: Using these research methods and models, it was possible to calculate the change in the efficiency of workers performing new tasks in the D&D process and the corresponding reduction in the work time and collective dose.

• Nuclear Engineering and Technology
• /
• 제56권1호
• /
• pp.160-166
• /
• 2024

The inversion of radiation field distribution is of great significance in the decommissioning sites of nuclear facilities. However, the radiation fields often contain multiple mixtures of radionuclides, making the inversion extremely difficult and posing a huge challenge. Many radiation field reconstruction methods, such as Kriging algorithm and neural network, can not solve this problem perfectly. To address this issue, this paper proposes an optimized inverse distance weighted (IDW) interpolation algorithm for reconstructing the gamma radiation field. The algorithm corrects the difference between the experimental and simulated scenarios, and the data is preprocessed with normalization to improve accuracy. The experiment involves setting up gamma radiation fields of three Co-60 radioactive sources and verifying them by using the optimized IDW algorithm. The results show that the mean absolute percentage error (MAPE) of the reconstruction result obtained by using the optimized IDW algorithm is 16.0%, which is significantly better than the results obtained by using the Kriging method. Importantly, the optimized IDW algorithm is suitable for radiation scenarios with multiple radioactive sources, providing an effective method for obtaining radiation field distribution in nuclear facility decommissioning engineering.

• 방사선산업학회지
• /
• 제18권1호
• /
• pp.89-93
• /
• 2024

Accidents at nuclear facilities and nuclear power plants led to leaks of large amounts of radioactive substances. Of the various radioactive nuclides released, ¹³⁷Cs are radioactive substances generated during the fission of uranium. Therefore, due to the high fission yield (6.09%), strong gamma rays, and a relatively long half-life (30 years), a rapid and efficient removal method and a study of adsorbents are needed. Accordingly, an adsorbent was prepared using Prussian blue (PB), a material that selectively adsorbs radioactive cesium. As a result of evaluating the adsorption performance with the prepared adsorbent, it was confirmed that 82% of the removal efficiency was obtained, and most of the cesium was rapidly adsorbed within 10 to 15 minutes. The purpose of this study was to adsorb cesium using the Prussian blue alginate bead and to compare the change in detection efficiency according to the amount of adsorbent added for quantitative evaluation. However, in this case, it is difficult to determine the detection efficiency using a standard source with the same conditions as the measurement sample, so the efficiency change of the HPGe detector according to the different heights of Prussian blue was calculated through MCNP simulation using certified standard materials (1 L, Marinelli beaker) for radioactivity measurement. It is expected to derive a relational equation that can calculate detection efficiency through an efficiency curve according to the volume of Prussian blue, quantitatively evaluate the activity at the same time as the adsorption of radioactive nuclides in actual contaminated water and use it in the field of nuclear facility operation and dismantling in the future.

• 한국콘텐츠학회:학술대회논문집
• /
• 한국콘텐츠학회 2011년도 춘계 종합학술대회 논문집
• /
• pp.29-30
• /
• 2011

원자력시설의 해체를 수행하는데 있어서 해체 대상 시설의 성격을 파악하는 것은 매우 중요하다. 해체 대상 원자력시설의 특성 자료 조사 결과는 해체 시 발생되는 폐기물의 양을 예측하고, 해체사업의 비용 산정에 크게 활용이 되며, 특성들의 그루핑을 통하여 일련의 예측 활동에서 훈련 집합으로 사용될 수 있다. 이를 목적으로 해체사업 대상 시설의 특성자료를 관리하는 시스템, DEFACS(DEcommissioning FAcility Characterization DB System)를 개발하였다. 이는 웹브라우저상에서 동작하며, 크게 특성에 따른 데이터의 입출력, 가공처리 등의 기능을 수행한다.

• 방사성폐기물학회지
• /
• 제9권2호
• /
• pp.87-92
• /
• 2011

본 논문은 극저준위폐기물 관리에 관한 중국의 정책과 규정들을 소개하고 있다. 오래된 시설의 중요한 해체 및 부지복구 프로그램에 주어진 바와 같이, 극저준위폐기물의 처분을 위한 새로운 시설의 필요성이 대두되고 있다. 여러가지 일반적인 설계원리들은 다중방벽에 의해 폐기물을 격리시키는 중저준위폐기물 처분시설과 같다. 콘크리트 방벽을 사용하는 것 대신에 벤토나이트 또는 고밀도 폴리에틸렌 멤브레인을 사용하는 것 외에 통상적으로 처분시설의 설계는 위해폐기물 처분시설의 설계와 같다 극저준위폐기물 처분시설 2개소의 공학적 설계가 소개되었다.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
• /
• pp.303-304
• /
• 2018

• 방사성폐기물학회지
• /
• 제20권3호
• /
• pp.349-356
• /
• 2022

Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Workers' radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers' radiation exposure, and improved the treatment process's efficiency. The shielding package's effect on workers' radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.

• Journal of Nuclear Fuel Cycle and Waste Technology
• /
• 제1권1호
• /
• pp.75-82
• /
• 2013

A large quantity of radioactive waste was generated during the decommissioning of the KRR and UCF. The radioactive waste was packed into 200 liter drums and 4m3 containers and these were temporarily stored onsite until their final disposal in the national repository facility. Some of the releasable waste was freely released and utilized for non-nuclear industries. The combustible wastes were treated by the utilization of an incinerator with a capacity of on average 20 kg/hr.