• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.345-350
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• 2003

The development of a prototype for a Bridge Transported Servo Manipulator (BTSM) system operating in a hot cell is introduced. Mechanical master-slave manipulators (MSMs) which are mounted on the hot cell wall cannot access all the areas for the equipment maintenance due to their reach limitation. The BTSM has been developed to overcome the limitation of access that is a drawback of the MSMs for the equipment maintenance. Wire driven mechanisms have been adopted to increase the handling capacity to weight. This system can be a useful reference for designing other devices in the nuclear industry.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.3
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• pp.279-298
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• 2019

This study comprehensively addresses recent progress at KAERI in waste treatment technology to cope with waste produced by pyroprocessing, which is used to effectively manage spent fuel. The goal of pyroprocessing waste treatment is to reduce final waste volume, fabricate durable waste forms suitable for disposal, and ensure safe packaging and storage. KAERI employs grouping of fission products recovered from process streams and immobilizes them in separate waste forms, resulting in product recycling and waste volume minimization. Novel aspects of KAERI approach include high temperature treatment of spent oxide fuel for the fabrication of feed materials for the oxide reduction process, and fission product concentration or separation from LiCl or LiCl-KCl salt streams for salt recycling and higher fission-product loading in the final waste form. Based on laboratory-scale tests, an engineering-scale process test is in progress to obtain information on the performance of scale-up processes at KAERI.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.3
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• pp.285-299
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• 2006

At the end of 2005, 443 nuclear reactors were operating in 32 countries worldwide. They had provided about 3,000 TWh, which was just over 16 percent of global electricity supply. With the generating capacity of 368 GWe in 2004, the spent fuel generation rate worldwide, now becomes at about 11,000 tHM/y. Projections indicate that cumulative amounts to be generated by the year 2020, the time when most of the existing NPP will be closed to the end of their licensed lifetime, may be close to 445,000 tHM. In this regard, spent fuel management is a common issue in all countries with nuclear reactors. Whatever their national policy and/or strategy is selected for the backend of the nuclear fuel cycle, the management of spent fuel will contribute an impending and imminent issues to be resolved in the foreseeable future. The 2nd Review Meeting of the Contracting Parties to the Joint Convention was held in Vienna from 15 to 24 May 2006. The meeting gave an opportunity to exchange information on the national policy and strategy of spent fuel management of the Contracting Parties, to discuss their situations, prospects and the major factors influencing the national policies in this field and to identify the most important directions that national efforts and international co-operation in this area should be taken. In this paper, an overview of national and global trends of spent fuel management is discussed. In addition, some directions are identified and recent activities of each Member States in the subject area are summarized.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.1 no.1
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• pp.55-64
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• 2003

In this study, the maintenance process by the servo manipulator has been developed for the parts of the equipment, which we unable to reach out by the Master-Slave Manipulator(MSM) in a hot cell. To do this, a virtual mock-up is implemented using the iか prototyping technology. Using this mock-up, the workspace of the manipulators in the hot cell and the operator's view through the wall-mounted lead glass have been analyzed. In addition, the path planning of the servo manipulator using the collision detection function of the virtual mock-up has been established. From these, the maintenance process for the parts of the equipment, which are located at the outside of the MSM's workspace using the servo manipulator has been proposed and verified through the graphic simulation. It is revealed that the proposed remote maintenance process of the equipment can effectively be used in the real hot cell operation. It is also believed that the implemented virtual mock-up of the hot cell can effectively be applied in analyzing the various hot cell operation and enhancing the reliability and safety in a hot cell remote handling for the spent fuel management.

• The Korean Journal of Nuclear Medicine Technology
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• v.12 no.3
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• pp.147-156
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• 2008

Purpose: All acts which are enforced from the radioactive iodine therapeutic team is a in its own way principle and provision. Therefore unification of all acts can not be appropriately. We will make the standard coherence. Materials & Methods: From 5 November, 2007 to 17 November 2007, we conducted a questionnaire survey of the nuclear medicine manager of 30 hospitals. The contents of a questionnaire is medical treatment section, patient management, prosecuting attorney section, waste management and safety supervision in about the patient and a questionnaire was drawn up in the method which selects an item. Results: 30 hospital agencies are operating purely for I-131 high dose ablation therapy. Diagnostic study and daily schedule had the difference of some. The most of education for the patients took charge of doctor and nurse. The satisfaction of education was evaluated as the high thing. The safety supervision of waste management accomplishment and Safety supervision the patient and the worker observed on the basis of atomic energy law. Conclusion: Specific standards with sufficient amount of information and practical contents should have been presented through the following data. However, it seems to be lacking in many aspects. Nevertheless, respondents rated 70.9%, which is relatively high, on the value of clinical utilization, and I am very thankful for the evaluation. For many years from now, it may seem necessary for a lot of research on the specific matters based on these data to be conducted.

• Nuclear industry
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• v.16 no.12 s.166
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• pp.6-13
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• 1996

96년 6월 25일 제245차 원자력위원회에서 `원자력 사업 추진 체제 조정 방안`을 확정함에 따라, 그 후속 조치로서 개정 추진하게 된 제13차 원자력법 중 개정 법률안이 96년 11월 30일 제17차 국회 본회의에서 의결되었다. 이번 개정으로 원자력 연구 개발에 필요한 재원을 안정적으로 확보하게 되었음은 물론, 원자력안전위원회의 신설로 58년 원자력법 제정에 따라 설치된 원자력위원회의 기능이 분리되었으며, 방사성 폐기물 관리 사업의 추진 체제가 효율적으로 정비되었다. 12월중 공포될 예정인 개정 원자력법의 주요 내용을 중심으로 개정 취지 및 배경, 개정 내용, 앞으로의 운영 방향 등에 대해 알아본다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.4
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• pp.405-418
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• 2019

Based on spent fuels characteristics from domestic nuclear power plants and a disposal scenario from the current basic plan for high-level radioactive waste management, an improved disposal system has been proposed that enhances disposal efficiency and economic effectiveness compared to the existing disposal system. For this purpose, two disposal canisters concepts were derived from the length of the spent fuel generated from the nuclear power plants. In the disposal scenario, the acceptable amount of decay heat for each disposal container was determined, taking into account the discharge and disposal times of spent fuels in accordance with the current basic plan. Based on the determined decay heat of the two types of disposal canisters and the associated disposal system, thermal stability analyses were performed to confirm their suitability to the proposed disposal system design requirement and disposal efficiency assessment. The results of this study confirm 20% reduction in the disposal area and 20% increase in disposal density for the proposed disposal system compared to the existing system. These results can be used to establish a spent fuel management policy and to design a viable commercial disposal system.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.51-58
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• 2006

Since 2002, more than 400 PWR spent nuclear fuel assemblies have been transported and stored on-site using transport casks in order to secure the storage capacity of PWR spent nuclear fuel of Kori nuclear power plant. The complete on-site transport system, which includes KN-12 transport casks, the related equipment and transport vehicles, had been developed and provided. KN-12 transport casks were designed, fabricated and licensed in accordance with Korean and IAEA's transport regulations, and the related equipment was also provided in accordance with the related regulations. The on-site transport and storage operation using two KN-12 casks and the related equipment has been conducted, and the strict Quality Control and Radiation Safety Management through the whole process has been carried out so as to achieve the required safety and reliability of the on-site transport of spent nuclear fuel.

• Nuclear Engineering and Technology
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• v.26 no.1
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• pp.54-62
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• 1994

The hydraulic properties of domestic natural clay/crushed rock mixture suggested as a candidate backfill material for the low and intermediate level waste repository were investigated. The dry density-water content relationship was studied to define an optimum water content that gives a maximum attainable dry density at constant compaction pressure. The hydraulic conductivities of clay/crushed rock mixture as a function of clay content were also measured. As the clay content decreased, the maximum attainable dry density increased and the optimum water content became more distinct. However the attainable density is not significantly sensitive to water content. The hydraulic conductivities of the mixture increased from 5 $\times$ 10$^{-12}$ m/s to 7 $\times$ 10$^{-10}$ m/s with clay content decreasing from 100 wt.% to 25 wt.% at dry density of 1.2 Mg/㎥. In case of dry density of 1.5 Mg/㎥, they maintain the lower values of 5 $\times$ 10$^{-12}$ m/s even at 25 wt.% clay content. The concept of effective clay dry density was suggested to estimate the hydraulic conductivity of the mixture. It was shown that the effective clay dry density concept can explain welt the hydraulic conductivities of the mixtures with various dry density and crushed rock content.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.117-123
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• 2003

In succession to the previous paper, the tritium injection system and the regeneration system of the tritium handling system are presented. Both systems should be placed inside glove boxes since there can be potential leakage of tritium from these systems. The tritium injection system should be capable of measuring the exact amount of the injected tritium to keep track of the tritium inventory. The tritium injection system is designed to recover the remaining tritium from the system after injection for the minimization of tritum release to the environment as well as for the recovery of precious resource. TRS equipment such as MS, Ni catalyst bed, and metal getter are regenerated with a standalone regeneration system. Unlike other equipments which can be regenerated by heating and purging with appropriate gas, regeneration of the metal getter used to recover tritium is somewhat complicated.