Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk information

Heo, Yunyeong; Lee, ChoongWie; Kim, Hee Reyoung; Lee, Seung Jun

doi:10.1016/j.nucengdes.2021.111624

Cited by 3 publications

(4 citation statements)

References 9 publications

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“…To reduce the dose that comes from radiological hazards, the following factors can be taken [26,30,32]: -Time. Time is directly proportionate with dose, so the dose can be effectively reduced by limiting the working time in radiation facilities [33].…”

Section: Evaluation Of Results and Identification Of Safety Measuresmentioning

confidence: 99%

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Tyas

Deswandri²,

Intaningrum³

et al. 2022

Tri Dasa Mega

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Decommissioning is the final stage of a nuclear reactor. In preparing the decommissioning plan, one of the important elements that need to be considered is safety assessment. During decommissioning, there are many complex tasks to be done where the radiological and non-radiological hazards arise and can significantly affect not only the workers but also the general public and the environment. Indonesia has no experience with nuclear reactor decommissioning, so it is necessary to study various experiences of decommissioning activities in the world. This study proposes a framework to implement the safety assessment on the decommissioning of the TRIGA 2000 research reactor. The framework was developed on desk-based research and analysis. The proposed framework involves the facility and decommissioning activities, hazard identification, hazard analysis, hazard evaluation, hazard or risk control, and independent review.

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Section: Evaluation Of Results and Identification Of Safety Measuresmentioning

confidence: 99%

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Tyas

Deswandri²,

Intaningrum³

et al. 2022

Tri Dasa Mega

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“…The subject of nuclear decommissioning is gaining more significance among governments, regulators, and industries because many nuclear power plants (NPP) will reach their end of life in the next 2 decades [1]. More than half of the world's NPPs are getting older and are passing 30 years old.…”

Section: Introductionmentioning

confidence: 99%

“…Fuzzy logic was chosen as the preferred method for determining the risk assessment model for NPP radioactive concrete structure decommissioning due to its ability to handle uncertainties and imprecisions inherent in expert judgments. While there are various tools available such as statistical analysis, machine learning, and artificial intelligence and used by others [1,37], fuzzy logic offers a well-established framework for capturing and processing linguistic uncertainties, which are common in risk assessment processes. Moreover, fuzzy logic allows for the integration of expert knowledge and subjective assessments, crucial in domains like nuclear decommissioning where empirical data may be scarce or difficult to obtain.…”

mentioning

confidence: 99%

Risk Evaluation of Radioactive Concrete Structure Decommissioning in Nuclear Power Plants Using Fuzzy-AHP

Moon,

Mirmotalebi,

Jang

et al. 2024

Buildings

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Over 50% of nuclear power plants (NPPs) worldwide have operated for over three decades, leading to a surge in decommissioning projects. This study addresses the gap in current guidelines by analyzing risks in nuclear decommissioning. Using the fuzzy-AHP technique, tasks within dismantling radioactive concrete structures are prioritized. Findings reveal structural and human-related risks across five main cutting tasks. Collision emerges as a significant concern, particularly during wire saw installation and concrete block hoisting hole creation. Subcategory risk priorities highlight variations in risk across tasks, with jamming, falling, and falling objects identified as top concerns during wire saw transportation. This study emphasizes the importance of comprehensive risk assessment in enhancing safety during decommissioning. It underscores the need to consider both physical risks and risks to personnel throughout the process. By prioritizing safety, stakeholders can ensure worker safety and operational efficiency while minimizing hazards. This research contributes to standardized safety protocols for nuclear decommissioning worldwide, aligning with sustainable energy practices. The outcomes offer practical insights for safety manual development and decision-making processes. This study represents progress in ensuring safety during nuclear decommissioning, paving the way for further refinement of safety protocols and guidelines tailored to decommissioning sites.

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“…Therefore, the powder can be used for recycled cement (RC) after crushing and burning more than twice [15]. Accordingly, instead of disposing of the powder, it is utilized as a solidifying agent for RC, leading to a decrease in the usage of common solidifying agents, such as Portland cement, as well as reducing the amount of waste and cost of disposal [16]. In addition, waste soil is generated from the decommissioning process, and it contains some clay minerals, such as illite and zeolite, which show an excellent capacity for adsorbing radioactive nuclides.…”

Section: Introductionmentioning

confidence: 99%

Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities

Jeon,

Lee,

Lee

et al. 2024

Applied Sciences

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Hundreds of thousands of tons of waste are generated from decommissioned nuclear- power facilities, and it has become a critical global issue to secure technology for reducing and recycling this waste. Concrete waste (CW) is estimated to comprise 60–80% of the total waste, and concrete-waste powder (CWP) includes enough inorganic substances used as effective materials for waste treatment. Accordingly, it can be used to produce recycled cement (RC). This study aimed to evaluate the performance of a solidification agent manufactured using recycled cement (SRC) for the safe packing of radioactive wastes, such as coarse aggregates of CW, waste soil, and metal wastes originating from decommissioned nuclear facilities. The experimental results indicated that the most relevant incineration temperature of CWP for RC was 700 °C. The optimum water-to-binder ratio was determined to be 0.4, and the most relevant substitution ratio of ground granulated blast furnace slag for CWP was determined to be 15%. In addition, calcium silicate hydrate is the most effective hydration product for improving the compressive strength of SRC. The maximum packing capacities of the SRC for coarse aggregates, waste soil, and metal waste, which were simulated as radioactive wastes, were determined to be 30, 5, and 7 wt%, respectively. The results of leaching tests using SRC containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the RC composed of CWP can be used as a solidifying agent to safely dispose of radioactive wastes, such as coarse aggregates, waste soil, and metal waste.

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Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk information

Cited by 3 publications

References 9 publications

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Risk Evaluation of Radioactive Concrete Structure Decommissioning in Nuclear Power Plants Using Fuzzy-AHP

Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities

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