• 에너지공학
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• 제29권1호
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• pp.63-74
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• 2020

영구정지 후 해체가 계획된 고리 1호기 원자력발전소는 해체 과정에서 다양한 종류의 방사성폐기물이 대량으로 발생할 것으로 예상되고 있다. 이 중 가장 많은 발생량을 차지할 것으로 예상되는 콘크리트 방사성폐기물에 대하여 기존 폐기물의 처분 현황 및 법적 제한사항등을 분석하여 적절하고 효율적인 처분방법을 마련하는 것은 중요한 사안일 것으로 판단된다. 콘크리트 방사성폐기물은 다양한 준위의 폐기물들이며, 이 중 규제해제 준위에 해당되어 자체처분이 가능한 폐기물은 바이오실드 콘크리트이다. 본 논문에서는 방사화 평가 결과를 바탕으로 자체처분이 가능한 폐기물을 자체처분 평가 코드인 RESRAD 코드 프로그램을 이용하여 자체처분 안전성 평가를 수행하였다. 대상 폐기물의 자체처분 시나리오를 선정하고 자체처분시 개인별 피폭선량을 계산하여 국내 원자력안전법에서 규정하는 자체처분 기준 제한치의 만족 여부를 판단하였다. 평가 결과, 전체적으로 상당히 낮은 결과 값을 보이며 기준 제한치를 만족하는 결과를 나타내었다. 이러한 자체처분 안전성 평가 결과를 바탕으로 규제해제 대상으로서 자체처분 가능한 바이오실드 콘크리트 폐기물에 대한 적절한 처분방법을 제시하였다.

• 방사선산업학회지
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• 제17권1호
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• pp.19-32
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• 2023

The amount of radioactive waste is expected to dramatically increase with decommissioning of nuclear power plants such as Kori-1, the first nuclear power plant in South Korea. Accurate nuclide analysis is necessary to manage the radioactive wastes safely, but research on verification of radionuclide analysis has yet to be well established. This study aimed to develop the technology that can verify the results of radionuclide analysis based on artificial intelligence. In this study, we propose an anomaly detection algorithm for inspecting the analysis error of radionuclide. We used the data from 'Updated Scaling Factors in Low-Level Radwaste' (NP-5077) published by EPRI (Electric Power Research Institute), and resampling was performed using SMOTE (Synthetic Minority Oversampling Technique) algorithm to augment data. 149,676 augmented data with SMOTE algorithm was used to train the artificial neural networks (classification and anomaly detection networks). 324 NP-5077 report data verified the performance of networks. The anomaly detection algorithm of radionuclide analysis was divided into two modules that detect a case where radioactive waste was incorrectly classified or discriminate an abnormal data such as loss of data or incorrectly written data. The classification network was constructed using the fully connected layer, and the anomaly detection network was composed of the encoder and decoder. The latter was operated by loading the latent vector from the end layer of the classification network. This study conducted exploratory data analysis (i.e., statistics, histogram, correlation, covariance, PCA, k-mean clustering, DBSCAN). As a result of analyzing the data, it is complicated to distinguish the type of radioactive waste because data distribution overlapped each other. In spite of these complexities, our algorithm based on deep learning can distinguish abnormal data from normal data. Radionuclide analysis was verified using our anomaly detection algorithm, and meaningful results were obtained.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.106-113
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• 2004

A major problem of nuclear energy is the production of radioactive wastes. Needs for more environmentally favorable method to decontaminate radioactive contaminants make the use of liquid/Supercritical $CO_2$ as a solvent medium. In removing radioactive metallic contaminants under $CO_2$ solvent, two methods - use of chelating ligands and that of water in $CO_2$ emulsion - are possible. In the chelating ligand method, a combination of ligands that can make synergistic effects seems important. We discuss about the properties of microemulsion formed by F-AOT. By adding acid in water core, decontamination of metallic parts, soils were possible.

• 대한핵의학회지
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• 제7권1호
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• pp.51-54
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• 1973

The use of ion-exchange resins for the treatment of radioactive wastes has many advantages, but thes eare rather expensive as compared with the Korean vermiculite. The Korean vermiculite has slightly different chemical constituents from the ones produced in other countries, and its physical properties might be applicable to the management of radioactive waste, in a small nuclear installation. The decontaminating effect of Korean vermiculite for the low-level radioactive liquid was investigated. $^{106}Ru,\;^{90}Sr,\;and\;^{137}Cs$ were utilized for the experiments. The removal rates by Korean vermiculite were calculated for $^{106}Ru,\;^{90}Sr\;and\;^{137}Cs$ and the removal rates increased as the weight of vermiculite in the exchange column increased. The decontaminating constants, $K_d$ of the Korean vermiculite for $^{106}Ru,\;^{90}Sr\;and\;^{137}Cs$ were 2.7, 69.3 and 263ml/g respectively. Through the results of experiments, the application of Korean vermiculite column to the treatment of low-level radioactive waste is quite feasible.

• Nuclear Engineering and Technology
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• 제39권6호
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• pp.697-702
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• 2007

Radioactive waste has been produced in the UK for many decades. Since the 1950' s much of this has been associated with civil nuclear power production and the nuclear weapons programme. There have been a number of unsuccessful attempts in the UK since the 1980s to deal with the waste and find suitable sites for its disposal. However, the UK Government has addressed this and in 2001 introduced the "Managing Radioactive Waste Safely" programme. The aim of this was to make decisions on the long-term radioactive waste management policy through stakeholder engagement. In 2006, it adopted a policy of geological disposal for higher activity wastes and following further consultations, is now at the stage of choosing how that policy should be implemented.

• 방사성폐기물학회지
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• 제13권1호
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• pp.45-53
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• 2015

1978년 고리 1호기의 상업 운전을 시작으로 현재 우리나라에서는 총 23기의 원전이 운영 중에 있다. 운영 중인 원전으로부터 방사성폐기물이 계속 발생되고 누적되어 갈 것이다. 또한 원전의 수명 연장과 신규 원전의 추가 건설 이외에도 제염해체 연구시설 등 각종 원자력 시설에서 발생하는 방사성폐기물은 꾸준히 증가하고 있다. 우리나라는 최근 IAEA에서 권고하는 신 분류기준을 적용한 신분류기준에 대해 원자력안전위원회 고시를 개정하였다. 중·저준위폐기물을 IAEA 신 분류기준을 적용하여 세분화한다면, 약 98%를 차지하는 저준위 및 극저준위 방사성폐기물과 규제면제폐기물을 효과적으로 처분 할 수 있게 된다. 본 논문에서는 신 분류기준을 적용한 해외 적용 사례와 처분 방안 현황을 분석하여 국내에 적용 가능한 최적의 합리적인 적용 방안 및 해체 방사성폐기물량을 산정해 보고자 한다.

• 시스템엔지니어링학술지
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• 제17권1호
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• pp.76-84
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• 2021

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.

• 방사성폐기물학회지
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• 제18권4호
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• pp.537-548
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• 2020

Currently, radioactive waste for disposal has been restricted to low and intermediate level radioactive waste generated during operation of nuclear power plants, and these radioactive wastes were managed and disposed of the 200 L and 320 L of steel drums. However, it is expected that it will be difficult to manage a large amount of decommissioning waste of the Kori unit 1 with the existing drums and transportation containers. Accordingly, the KORAD is currently developing various and large-sized containers for packaging, transportation, and disposal of decommissioning waste. In this study, the radiation exposure doses of workers and the public were evaluated using RADTRAN computational analysis code in case of the domestic on-road transportation of new package and transportation containers under development. The results were compared with the domestic annual dose limit. In addition, the sensitivity of the expected exposure dose according to the change in the leakage rate of radionuclides in the waste packaging was evaluated. As a result of the evaluation, it was confirmed that the exposure dose under normal and accident condition was less than the domestic annual exposure dose limit. However, in the case of a number of loading and unloading operations, working systems should be prepared to reduce the exposure of workers.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.117-118
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• 2004

국내 TRIGA Mark II&III 및 우라늄 변환시설 해체시 다량의 금속폐기물 발생이 예상되며, 현재 이러한 저준위 방사성 금속폐기물을 처리, 재활용하는 기술들에 대한 연구가 국$\cdot$내외적으로 활발히 수행 중에 있다. 이에 본 연구에서는 해체시 발생하는 금속폐기물의 효율적인 감용 및 재활용에 관한 국내외 처리 기술을 검토하여 국내 TRIGA Mark II&III 및 우라늄 변환시설에서 발생하는 해체 금속폐기물의 처리 방안을 수립하기 위한 정보를 제공하고자 한다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.133-134
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• 2004

DUPIC (Direct Use of spent PWR fuel In CANDU) fuel cycle technology is being developed at Korea Atomic Energy Research Institute (KAERI). All the DUPIC fuel fabrication processes are remotely conducted in the completely shielded M6 hot-cell located in the Irradiated Material Examination Facility (IMEF) at KAERI. Undesirable products such as spent nuclear fuel powder debris and contaminated wastes are inevitably created during the DUPIC nuclear fuel fabrication processes.(omitted)