• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.413-414
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.441-442
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• 2009

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.11a
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• pp.67-68
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• 2007

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2018.11a
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• pp.173-174
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• 2018

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2017.10a
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• pp.119-120
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• 2017

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2017.05a
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• pp.118-119
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• 2017

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.572-578
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• 2003

In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.21 no.3
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• pp.359-370
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• 2023

The thermal integrity of spent nuclear fuels has to be maintained during their long-term dry storage. The detailed temperature distributions of spent fuel assemblies are essential for evaluating the integrity of their dry storage systems. In this study, a subchannel analysis model was developed for a canister of a single fuel assembly using the COBRA-SFS code. The thermal parameters affecting the peak cladding temperature (PCT) of the spent fuel assembly were identified, and sensitivity analyses were performed based on these parameters. The subchannel analysis results indicated the presence of a recirculation flow, based on natural convection, between the fuel assembly and downcomer region. The sensitivity analysis of the thermal parameters indicated that the PCT was affected by the emissivity of the fuel cladding and basket, convective heat transfer coefficient, and thermal conductivity of the fluid. However, the effects of the wall friction factor of the canister, form loss coefficient of the grid spacers, and thermal conductivities of the solid materials, on the PCT were predominantly ignored.

• Journal of Radiation Industry
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• v.18 no.1
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• pp.43-52
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• 2024

Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spent nuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measure to this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan for dry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operated in various ways, and to select the optimal dry storage method, the reduction of exposure for workers must be considered. Accordingly, it is necessary to develop a worker exposure scenario according to the dry storage method and evaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposure scenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedure of the foreign commercial spent nuclear fuel dry storage system was analyzed based on the Final Safety Analysis Report (FSAR). 1) the concrete overpack-based system, 2) the metal overpack-based system, and 3) the vertical storage module-based system were selected for analysis. Factors were assumed that could affect the type of work (working distance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processes involved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developed accordingly. The concrete overpack method, the metal overpack method, and the vertical storage module method were classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number of workers for each process were set. The product of working hours and number of workers (Man-hour) was set high in the order of concrete overpack method, vertical storage module method, and metal overpack method, and short-range work (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to be used as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclear fuel.

• The Korean Journal of Nuclear Medicine Technology
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• v.12 no.1
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• pp.3-12
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• 2008

Purpose: Contaminated clothes and bedclothes of patients by mouth or with excrement are produced after Radioisotope $^{131}I$ treatment. In this paper, patient's clothes and bedclothes contaminated by radioactivity measured and radioactive waste wish to calculate optimum storage period. Material and Methods: The whole area of patients' clothes and bedclothes measured 70 patients, 12 males and 58 females, who had radioisotope $^{131}I$ therapy between August 2005 and February 2006. Assuming contamination is evenly distributed, the radioscope used to measure up to social toleration level at 7 day intervals. Results: Each optimum storage period of control group of 60 case and non control group of 10 case were average $44{\pm}16$ days and $32{\pm}13$ days. Decontamination effect of surface contamination for radioactive waste was average $83.66{\pm}15.15%$. Conclusion: It is important that classify radioactive waste according to difference of surface contamination. Result of this research, handling radioactive waste in optimum storage period may be useful.