• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.327-331
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• 2001

The Pohang Neutron Facility based on an electron linac was constructed in order to construct the infrastructure for nuclear data production in Korea. It consists of a 100-MeV electron linac, a water-cooled Ta target, and an 11-m time-of-flight path. We measured the time-of-flight path length, the neutron energy spectra for different water levels inside the moderator, and the neutron total cross sections of polyethylene and copper by the transmission method.

• 한국방사선학회논문지
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• 제2권3호
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• pp.27-31
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• 2008

고에너지 X-ray를 사용하는 방사선 이용 시설에서는 고에너지 광자에 의한 광중성자 등의 발생에 대한 방사선방호 조치가 방사선 안전의 관점에서 매우 중요한 이슈 중의 하나이다. 이러한 광중성자들은 시설 외부로 누설될 경우 skyshine effect에 의해 작업종사자 및 일반 대중에게 예기기 않은 방사선 피폭을 야기할 수 있다. 이 논문에서는 9MeV X-ray를 이용한 화물검색시설을 대상으로 몬테카를로법을 이용하여 광중성자 생성량을 계산하고 이를 통해 시설 외부에서의 중성자 skyshine 방사선량률을 평가하였다.

• 한국주거학회논문집
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• 제17권5호
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• pp.1-8
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• 2006

Being rapidly increased in population of the elderly, the welfare of the elderly is no longer family's and personal problems. It is a social issue that have to be solved by the community and the government. Daejeon city government faces the same social issue and should release the solution to the community in the near future. Based on the new trend of deinstitutionalization and community care for the elderly who live in normal home rather than for those in protection systems, the solution could be released to the elderly. This paper is assessed as the first stage research of normalization of the old people's living. By the comparition analysis of the existing Senior Welfare Center in Daejeon city and Japan, the facility space improvement method was considered. And through the above investigation and comparition analysis, the method that extend and improve the welfare facility space of Senior Welfare Center is proposed.

• 국제학술발표논문집
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• The 3th International Conference on Construction Engineering and Project Management
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• pp.1128-1133
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• 2009

Recently super complex culture shopping facility development seeks consumer' convenience present and are coming restaurant neighborhood, cinema, shopping, hotel etc, according to intensive plan. Such as complex culture shopping facility was developed to most subway station area center and have concept that is space for a main facilities or space for environment protection, citizens' a rest in city. Howeve,r space of recently domestic large size complex culture shopping facility that do not plan systematically was lacking and caused result that do not use efficiently space. Limited extent of research that define complex culture shopping equipment and analyze form of space and present space planning with analysis of research connected with complex usage development.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.388.1-388
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• 1999

• Corrosion Science and Technology
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• 제4권6호
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• pp.242-249
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• 2005

A lot of parts in FGD (Flue Gas Desulfurization) systems of fossil-fuel power plants show the environments in which are highly changeable and extremely acidic corrosive medium according to time and locations, e.g. in duct works, coolers and re-heaters etc. These conditions are formed when system materials are immersed in fluid that flows on them or when exhausted gas is condensed into thin layered acidic medium to contact materials of the system walls and roofs. These environments make troublesome corrosion and air pollution problems that are occurred from the leakage of the condensed solution. To cathodically protect the metallic structures in extremely acidic fluid, the properties of the protective coatings on the metal surface were very important, and epoxy Novolac coating was applied in this work. On the base of acid immersion tests, hot sulfuric acid decreased the hardness of the coatings and reduced greatly the content of $Na_2O$, $Al_2O_3$, and $SiO_2$ among the main components of the coating. A special kind of CP(Cathodic Protection) system has been developed and tested in a real scale of the FGD facility. Applied coating for this CP system was peeled off and cracked in some parts of the facility. However, the exposed metal surface to extremely acidic fluid by the failure of the coatings was successfully protected by the new CP system.

• Journal of Radiation Protection and Research
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• 제32권4호
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• pp.190-193
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• 2007

The objective of this study is to recommend the radiation protection design parameters from the shielding point of view for concrete wall between the decay tank room and the primary pump room in TRIGA Mark-II Research Reactor Facility. The shield design for this concrete wall has been performed with the help of Point-kernel Shielding Code Micro-Shield 5.05 and this design was also validated based on the measured dose rate values with Radiation Survey Meter (G-M Counter) considering the ICRP-60 (1990) recommendations for occupational dose rate limit ($10{\mu}Sv/hr$). The recommended shield design parameters are: (i) thickness of 114.3 cm Ilmenite-Magnetite Concrete (IMC) or 129.54 cm Ordinary Reinforced Concrete (ORC) for concrete wall A (ii) thickness of 66.04 cm Ilmenite-Magnetite Concrete (IMC) or 78.74 cm Ordinary Reinforced Concrete (ORC) for concrete wall B and (iii) door thickness of 3.175 cm Mild Steel (MS) on the entrance of decay tank room. In shielding efficiency analysis, the use of I-M concrete in the design of this concrete wall shows that it reduced the dose rate by a factor of at least 3.52 times approximately compared to ordinary reinforced concrete.

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.447-454
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• 2009

This paper is a technical review of the research and development results of the Korea Nuclear Instrumentation and Control System (KNICS) project and Nu-Tech 2012 program. In these projects man-machine interface system architecture, two digital platforms, and several control and protection systems were developed. One platform is a Programmable Logic Controller (PLC) for a digital safety system and another platform is a Distributed Control System (DCS) for a non-safety control system. With the safety-grade platform PLC, a reactor protection system, an engineered safety feature-component control system, and reactor core protection system were developed. A power control system was developed based on the DCS. A logic alarm cause tracking system was developed as a man-machine interface for APR1400. Also, Integrated Performance Validation Facility (IPVF) was developed for the evaluation of the function and performance of developed I&C systems. The safety-grade platform PLC and the digital safety system obtained approval for the topical report from the Korean regulatory body in February of 2009. A utility and vendor company will determine the suitability of the KNICS and Nu- Tech 2012 products to apply them to the planned nuclear power plants.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.503-508
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• 2003

원자력 시설의 공기조화 시스템은 일반시설의 공기조화 시스템에 비하여 더 안정되고 여유있게 설치 및 시공되어야 한다. 그 목적은 최적 작업환경유지, 오염 공기로부터의 작업자 보호, 외부배기로 인한 대기오염 방지 등이다. 낮은 공기오염조차 막는 것이 원자력시설의 안전한 운전을 위해 기본적인 것이다. 설계 시 시스템의 융통성을 갖는 설계가 필요한데 이는 나중에 시스템의 수정보완 등을 고려할 때 중요하다. 본 논문에서는 원자력시설의 공기조화계통 설계에 고려해야 할 내용 및 외국시설에 대하여 검토하였는바, 원자력시설의 공기조화계통 설계에 활용될 수 있겠다.

• Nuclear Engineering and Technology
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• 제47권7호
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• pp.915-923
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• 2015

Pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems in Korea. The Korea Atomic Energy Research Institute, Daejeon, Korea has been studying pyroprocess technology, and the conceptual design of an engineering-scale pyroprocess facility, called the Reference Engineering-scale Pyroprocess Facility, has been performed on the basis of a 10 ton heavy metal throughput per year. In this paper the concept of Reference Engineering-scale Pyroprocess Facility is introduced along with its safety requirements for the protection of facility workers, collocated workers, the off-site public, and the environment. For the identification of safety structures, systems, and components and/or administrative controls, the following activities were conducted: (1) identifying hazards associated with operations; (2) identifying potential events associated with these hazards; and (3) identifying the potential preventive and/or mitigative controls that reduce the risk associated with these accident events. This study will be used to perform a safety evaluation for accidents involving any of the hazards identified, and to establish safety design policies and propose a more definite safety design.