• Journal of the Korea Society of Computer and Information
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• v.18 no.11
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• pp.201-212
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• 2013

This study divides and traces experience courses of families' disorganization and reorganization of North Korean refugees in North Korea, China, and South Korea after settlement respectively, from the course of their escaping North Korea to entering South Korea. Through these results, the study is to propose political implications. Main data for the study were analyzed through a case study as a qualitative study method, targeting eight people from July in 2012 to March in 2013. From the study result, though North Korean refugees seemed to disorganize and leave family relations in the course of escaping North Korea, it was found out that this is not disorganization but a preparatory stage which saves families standing at the crossroads of life and death and makes a chance to live with them someday. In these courses, in order for them to overcome their situations and survive, while repeating disorganization and reorganization of families, they used them as a way of saving themselves and their families. It was discovered that these phenomena always occurred simultaneously.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.3
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• pp.265-273
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• 2006

In the decommissioning and decontamination(D&D) planning stage, it is important that the scenarios are evaluated from an engineering point of views because the decommissioning work has to be executed economically and safely by following the best scenarios. Therefore, we need to develope several modules to evaluate the decommissioning scenarios. In this paper, the digital mock-up system is constructed in the virtual space to simulate the whole decommissioning process. The schedule evaluating equation and cost evaluation equation are derived to calculate the working time and the expected cost. And in order to easily identify the radiation level about the activated objects, the radiation visualization module is developed. Finally, on the basis of the obtained results from the Digital Mock-up and other important factors, the evaluating method of the scenarios that can indicate the best scenario is described.

• Journal of Energy Engineering
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• v.16 no.3
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• pp.93-102
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• 2007

This paper presents a scenario evaluation model of the AHP (Analytic Hierarchy Process) to evaluate dismantling scenarios considering quantitative and qualitative considerations. And decommissioning information producing modules which can obtain a dismantling schedule, quantify radioactive waste, visualize a radioactive inventory, estimate a decommissioning cost, and estimate a worker's exposure was developed to assess qualitatively decommissioning information. The digital mock-up (DMU) system was developed to verify dismantling processes and find error of scenarios in virtual space. It combines and manages the decommissioning information producing modules, the decommissioning DB, and the dismantling evaluation module synthetically. By using AHP model and DMU system, the thermal column in KRR-1 was evaluated on plasma arc cutting scenario and nibbler cutting scenario using the developed decommissioning DMU system.

• Proceedings of the Korea Information Processing Society Conference
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• 2004.05a
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• pp.85-88
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• 2004

해체 활동 시작 단계에서부터 최종처리까지 발생되는 일련의 모든 자료를 체계적이고 과학적으로 관리할 수 있는 해체 DB structure를 구축하기 위하여 해체 정보 전략 계획을 수립하였고, 해체 DB 정보 영역을 분류하여 세부항목을 도출하였으며, 시스템 개발 도구 및 운영환경을 설정하였다. 자료흐름도(DFD)와 개체 관계도(ERD)를 이용하여 해체 자료 구조를 최적화하였고, Prototype 과정을 거쳐 해체 자료가 체계적으로 저장 관리 될 수 있도록 프로그램을 개발 하였다. 현재(2001년6월부터 2003년12월)까지 연구로 해체활동을 통해 발생한 해체 현장 자료를 이용하여 해체 DB 시스템을 시험한 결과 무작위로 데이터를 추출하여 집계한 결과와 잘 일치하고 있음을 확인하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.4
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• pp.355-367
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• 2017

The decommissioning of Kori unit 1, which was permanently shut down in June of 2017, will be the first instance of the dismantling of a commercial nuclear power plant in Korea. The disposal of waste during the dismantling process accounts for a large part of the total decommissioning cost. Therefore, structures consisting of activated and contaminated concrete must be economically and safely dismantled by establishing a proper dismantling strategy. This study focuses on optimized dismantling and disposal scenarios pertaining to a biological shield. Several dismantling cases, regulations and technologies related to waste treatment as these practices pertain to nuclear power plants are analyzed. To minimize the amount of waste from the biological shield dismantling process, an optimized dismantling scenario is presented and disposal alternatives for dismantled concrete waste are proposed.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.58-71
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• 2004

Korea Research Reactor (KRR) 1＆2 has shut down and through preparatory activities, its decommissioning activities are underway. As its decommissioning activities have been done over several years, its relevant data have been spreaded with various type and media all over the discrete place and inadvertently managed, As a result, managing and assessing data of KRR 1＆2 has been difficult and complex and its data cannot be evaluated. By developing the decommissioning database system of KRR 1＆2 the data of decommissioning activities can be correctly evaluated, being systematically managed and objectively assessed. Finally, the decommissioning project of KRR 1＆2 have come to more effectively accomplished. As the data of decommissioning activities can be at last systematically analyzed and objectively assessed, the decommissioning project of KRR 1＆2 would be more effectively accomplished.

• Korean Journal of Construction Engineering and Management
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• v.15 no.6
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• pp.63-70
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• 2014

Deconstruction of the building must be applied firstly in order to improve recycling and reuse of construction wastes. In this study have done a case study for deconstruction of an apartment. All construction waste(CW) which will be generated during deconstruction was examined in each part of the building. Because drawing did not exist in most of the old building, we drew up floor plans of buildings. After analyzing these drawings, estimated quantities of CW. It was measured working time of labor and equipments for deconstruction and general demolition on each building of the apartment. In addition, it was proposed in the volume and weight per unit after analyzing detailed measurement of CW which was generated in the process of deconstruction and traditional demolition. It suggested recovery rate at a site, volume and weight conversion factors, and waste basic unit per area that based on the results of comparative analysis on the amount of CW which is calculated from drawing and generated at a site. These factors will be used fundamental materials for estimating quantities and treatment cost of CW, and scheduling of works.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.681-686
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• 2003

It has been designed GUI(graphic user interface) to consult the convenience of a input data and the flexibility that can be retrieved dismantling information relation to decommissioning DB of KRR1&2. The GUI can proceed an input materials and a search and output of a saved data in server based on a facility code and also have a function of explorer which can find the lower dismantling objects in each facilities. It has added the structure of the multimedia that could be showed a series of dismantling activities with a Mpeg and pictures into the GUI. In the future work, Decommissioning DB and User Interface are intend to contribute a functions that could be evaluate and analyze for a dismantling activities with a engineering theory.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.2
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• pp.165-169
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• 2014

In order to use the nuclear energy as the sustainable energy source, the safe and efficient management of radioactive wastes generated from the nuclear fuel cycle including NPP decommissioning is one of the most important factors. The establishment of acceptance criteria for very low level radioactive wastes generated from decommissioning of nuclear power plant in a large quantity is seemed to play a key role for developing a radioactive wastes disposal strategy as well as NPP decommissioning strategy. In this thesis, we want to review the acceptance criteria of low-and-intermediate-level radioactive wastes in this country through the analysis of other country's acceptance criteria.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.1199-1204
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• 2003

The 3D simulations of the shielding concrete and the Rotary Specimen Rack(RSR) in the Korea Research Reactor-1&2(KRR-1&2) were carried out in present work. Four main dismantling processes, which are the removal of the RSR, reactor core region, beam tube, and thermal column and activated concrete, were selected for the graphic simulation by the consideration of the activation, worker training, work difficulty and so on. On the basis of these, we constructed their 3D CAD models and then drawn and reviewed their dismantling processes. In this study, the 3D simulation results of the shielding concrete and the RSR among main components are also presented and discussed.