• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.317-317
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• 1999

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.1
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• pp.11-39
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• 2018

Tritium and $^{14}C$ are two most important radionuclides released from nuclear facilities to the environment, and $^{14}C$ contributes dominant radiation dose to the population around nuclear power plants. This paper presents an overview of the production, pathway, species and levels of tritium and $^{14}C$ in nuclear facilities, mainly nuclear power plants. The methods for sampling and collection of different species of tritium and $^{14}C$ in the discharge gas from the stack in the nuclear facilities, atmosphere of the nuclear facilities and environment are presented, and the features of different methods are reviewed. The on-line monitoring methods of gaseous tritium and $^{14}C$ in air and laboratory measurement methods for sensitive determination of tritium and $^{14}C$ in collected samples, water and environmental solid samples are also discussed in detailed. Meanwhile, the challenges in the determination and speciation analysis of tritium and $^{14}C$ are also highlighted.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.19 no.1
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• pp.61-74
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• 2021

A paradigm shift in the government's energy policy was reflected in its declaration of early closure of old nuclear plants as well as cancellation of plans for the construction of new plants. To this end, unit 1 of Kori Nuclear Power Plant was permanently shut down and is set for decommission. Based on these changes, the off-site transport of spent fuels from nuclear power plants has become a critical issue. The purpose of this study is to develop an optimized method for transportation of spent fuels from Kori Nuclear Power Plant's units 1, 2, 3, and 4 to an assumed interim storage facility by simulating the scenarios using the Flexsim software, which is widely used in logistics and manufacturing applications. The results of the simulation suggest that the optimized transport methods may contribute to the development of delivery schedule of spent fuels in the near future. Furthermore, these methods can be applied to decommissioning plan of nuclear power plants.

• Korean journal of communication and information
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• v.25
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• pp.7-40
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• 2004

Today, nuclear energy conflict is caused from the dangerous radioactive material. The main party of this conflict are politic and economic systems which deride nuclear energy, and the persons concerned which it oppose and the anti-nuclear environment group. If the nuclear waste is transported from one nation to another nation, multi national anti-nuclear group appears as conflict party. We call this domestic and transnational risk communication new social movement. From the viewpoint of system theory, the new social movement can mean the offensive development of self-reference which withstand the "technicalization of communication" through the "symbolically generalized communication media" like money and power. By comparing Northeast Asia and Europe, the nuclear energy conflict did not show a big difference in the selection of nuclear waste storing site. In the Northeast Asia, when Taiwan exports the nuclear waste to North Korea, the international conflict broke out. In Europe, Germany has a hard experience with the construction-plan for the re-treating plant that produces the plutonium from the dangerous nuclear waste, and with the transnational transport of the nuclear waste. The new social movement aims the global paradigm which is able to guarantee the subtainability of ecological environment. The nuclear conflict in the "world risk society" is solved through the "discourse-alliance" which accomplishes sub-politics by crossing the border of class, nation and system.

• Nuclear Engineering and Technology
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• v.11 no.3
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• pp.213-217
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• 1979

• Nuclear industry
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• v.20 no.6 s.208
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• pp.52-54
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• 2000

• Nuclear Engineering and Technology
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• v.55 no.4
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• pp.1495-1506
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• 2023

For the safe disposal of high-level radioactive waste using Engineered Barrier Systems (EBS), bentonite buffer is used by its high swelling capability and low hydraulic conductivity. When the bentonite buffer is contacted to heated pore water containing ions by radioactive decay, chemical alterations of minerals such as illitization reaction occur. Illitization of bentonite indicates the alteration of expandable smectite into non-expandable illite, which threatens the stability and integrity of EBS. This study intends to provide a thorough review on the information underlying in the illitization of bentonite, by covering basic clay mineralogy, smectite expansion, mechanisms and observation of illitization, and illitization in EBS. Since understanding of smectite illitization is crucial for securing the safety and integrity of nuclear waste disposal systems using bentonite buffer, this thorough review study is expected to provide essential and concise information for the preventive EBS design.

• Proceedings of the Korean Institute of Building Construction Conference
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• 2021.11a
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• pp.156-157
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• 2021

Since concrete is contaminated or radioactive during operation of nuclear power plants, it is the most important radioactive waste generated during the dismantling of a nuclear power plant. The amount of waste is different depending on the pollution state of each facility and the applied technology is different, so there is a big difference. We aim to reduce the amount of waste and increase the value of recyclability through technology to remove radionuclides attached to the surface. For this purpose, laser scabbling, which exfoliates the surface of concrete by irradiating a laser, and a facility system for controlling dust and dust are used in parallel. The purpose of this study is to evaluate the efficiency of laser scabbling by manufacturing simulated concrete for nuclear facilities, and to review the optimal mixing design conditions for nuclear facility structures.

• Nuclear Medicine and Molecular Imaging
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• v.42 no.4
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• pp.261-266
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• 2008

We established a model to calculate radioactive waste from sewage disposal tank of hospitals to optimize the number of patients receiving inpatient radioiodine therapy within the safety guideline in our country. According to this model and calculation of radioactivity concentration using the number of patients per week, the treatment dose of radioiodine, the capacity and the number of sewage tanks and the daily amount of water waste per patient, estimated concentration of radioactivity in sewage waste upon disposal from disposal tanks after longterm retention were within the safety guideline (30 Bq/L) in all the hospitals examined. In addition to the fact that we could increase the number of patients in two thirds of hospitals, we found that the daily amount of waste water was the most important variable to allow the increase of the number of patients within the safety margin of disposed radioactivity. We propose that saving the water amount be led to increase the number of patients and they allow two patients in an already furnished hospital inpatient room to meet the increasing need of inpatient radioiodine treatment for thyroid cancer.

• Nuclear Engineering and Technology
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• v.54 no.7
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• pp.2427-2434
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• 2022

Series of unequal quantity Nd/Ce co-doped ceramic nuclear waste forms, (Gd, Nd)₂(Zr, Ce)₂O₇, were prepared to tailor its ordered pyrochlore or disordered fluorite structure. The phase transition, microtopography, and elemental composition of the ceramic samples were systematically investigated, especially the effect of order-disorder structure on the chemical stability. It was confirmed that unequal quantity of Nd/Ce could synchronously replace the Gd/Zr-sites of Gd₂Zr₂O₇. And the phase transition of order-disorder structure could be successfully tailored by regulating the average cationic radius ratio of (Gd, Nd)₂(Zr, Ce)₂O₇ series. The elements of Gd, Nd, Zr, and Ce are uniformly distributed in the ordered or disordered structures. The MCC-1 leaching results showed that (Gd, Nd)₂(Zr, Ce)₂O₇ pyrochlore ceramic nuclear waste forms had excellent chemical stability, whose elements' normalized leaching rates were as low as 10^-4-10^-7 g·m^-2·d^-1 after 7 days. In particular, the chemical stability of disordered structure was superior to that of ordered structure. It was proposed that the force constant and the closest packing were changed with the structure transformation resulting the chemical stability difference.