• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.299.2-299
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• 1999

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2019.05a
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• pp.179-180
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• 2019

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2017.05a
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• pp.181-182
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• 2017

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2017.05a
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• pp.173-174
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• 2017

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.110-116
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• 2020

As the management plan for domestic spent nuclear fuel is delayed, the storage of the operating nuclear power plant is approaching saturation, and the Kori 1 Unit that has reached its end of operation life is preparing for the dismantling plan. The first stage of dismantling is the transfer of spent nuclear fuel stored in storage at plants. The spent fuel management process leads to temporary storage, interim storage, reprocessing and permanent disposal. In this paper, the technical issues to be considered when transporting spent fuel in this process are summarized. The spent fuels are treated as high-level radioactive waste and strictly managed according to international regulations. A series of integrity tests are performed to demonstrate that spent fuel can be safely stored for decades in a dry environment before being transferred to an intermediate storage facility. The safety of spent fuel transport container must be demonstrated under normal transport conditions and virtual accident conditions. IAEA international standards are commonly applied to the design of transport containers, licensing regulations and transport regulations worldwide. In addition, each country operates a physical protection system to reduce and respond to the threat of radioactive terrorism.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2004.10a
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• pp.1013-1016
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• 2004

High level radioactive wastes, such as spent fuels generated from nuclear power plant, will be disposed in a deep geological repository. To maintain the integrity of the disposal canister and to carry out the process effectively, the emplacement process for the canister system in borehole of disposal tunnel should be well defined. In this study, the concept of the disposal canister emplacement process for deep geological disposal was established. To do this, the spent fuel arisings and disposal rate were reviewed. Also, not only design requirements, such canister and disposal depth but also preliminary repository layout concept were reviewed. Based on the requirements and the other bases, the canister emplacement process in the borehole of the disposal tunnel was established. The established concept of the disposal canister emplacement process will be improved continuously with the future studies. And this concept can be effectively used in implementing the reference repository system of our own case.

• Computational Structural Engineering
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• v.8 no.1
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• pp.107-113
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• 1995

Spent fuel storage pool should maintain its structural integrity and the safety of stored spent fuels against design earthquake load. In this study, the seismic response analysis of the pool with LRB isolation system is performed for two different earthquakes. To investigate the seismic response of the base isolated pool, the analysis results are compared with the responses of conventional type. In conclusion, the base-isolation system is effective to reduce the seismic forces transmitted to the superstructure and the responses, and to secure the safety of the storage pool and stored spent fuel.

• 제어로봇시스템학회:학술대회논문집
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• 2001.10a
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• pp.123.3-123
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• 2001

To recycle the uranium resources in the spent nuclear fuels, all the fuel rods are extracted from the spent fuel assemblies. The remaining components of the spent fuel assembly after extracting all the rods, so called a NFBC(Non-Fuel Bearing Components), should be compacted to minimize the waste volume. To this present, KAERI (Korea Atomic Research Institute) has developed he NFBC compactor by introducing a new concept of cutting and compaction, In this paper, to achieve he maximum compaction ration of the NFBC volume while reducing compactor size, an fuzzy controller, which determines the reference force of the compactor, is proposed with using he fuzzy-inference.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11b
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• pp.86-91
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• 2005

A metal product obtained from an electrolytic reduction process, possesses less volume and radioactivity than those of the unprocessed spent oxide fuels. The chemical composition of the metal product varies according to the process condition. In this work, a basic study was performed to evaluate the chemical forms of the spent oxide fuel components in an electrolytic reduction process with the operation conditions. One of the most important operation conditions is the cell potential applied for the reduction cell. It is expected that $PU_{2}O_3$ is difficult to reduce even though the cell potential is negative enough to reduce the lithium oxide when the activity of $Li_{2}O$ exceeds 0.003. The reduction of actinide oxides via the reduction of $Li_{2}O$ is assumed to have a greater reduction yield than a direct reduction of the actinide oxides.

• Nuclear Engineering and Technology
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• v.10 no.1
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• pp.26-36
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• 1978

Numerical computations of radioactivities and decay energies in a spent fuel have been carried out for designing of a hot cell. Optimum wall and window thicknesses that can preserve spent fuel rods for experimental purposes are estimated with burnup rate of 33,000 MWD/T(U) which is nearly maximum from a pressurized water reactor such as the Go-Ri Unit 1. Before putting the spent fuels into a hot cell, it is assumed for thickness estimates of shield materials that they are cooled in a storage tay for several lime intervals. Considered are various types of shield materials through which changing the distances from a source to an observation point is also made.