• Proceedings of the SAREK Conference
• /
• 2003.07a
• /
• pp.215-215
• /
• 2003

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2017.10a
• /
• pp.235-236
• /
• 2017

• Journal of Radiation Protection and Research
• /
• v.28 no.2
• /
• pp.127-135
• /
• 2003

The primary contributors to the total occupational radiation exposure in operating nuclear power plants are operation and maintenance activities doting refueling outages. The Advanced Power Reactor 1400 (APR1400) includes a number of design improvements and plans to utilize advanced maintenance methods and robotics to minimize the annual collective dose. The major radiation exposure reduction features implemented in APR1400 are a permanent refueling pool seal, quick opening transfer tube blind flange, improved hydrogen peroxide injection at shutdown, improved permanent steam generator work platforms, and more effective temporary shielding. The estimated average annual occupational radiation exposure for APR1400 based on the reference plant experience and an engineering judgment is determined to be in the order of 0.4 man-Sv, which is well within the design goal of 1 man-Sv. The basis of this average annual occupational radiation exposure estimation is an eighteen (18) month fuel cycle with maintenance performed to steam generators and reactor coolant pumps during refueling outage. The outage duration is assumed to be 28 days. The outage work is to be performed on a 24 hour per day basis, seven (7) days a week with overlapping twelve (12) hour work shifts. The occupational radiation exposure for APR1400 is also determined by an alternate method which consists of estimating radiation exposures expected for the major activities during the refueling outage. The major outage activities that cause the majority of the total radiation exposure during refueling outage such as fuel handling, reactor coolant pump maintenance, steam generator inspection and maintenance, reactor vessel head area maintenance, decontamination, and ICI & instrumentation maintenance activities are evaluated at a task level. The calculated value using this method is in close agreement with the value of 0.4 man-Sv, that has been determined based on the experience aid engineering judgement. Therefore, with the As Low As Reasonably Achievable (ALARA) advanced design features incorporated in the design, APR1400 design is to meet its design goal with sufficient margin, that is, more than a factor of two (2), if operated on art eighteen (18) month fuel cycle.

• Journal of the Korean Home Economics Association
• /
• v.29 no.2
• /
• pp.17-34
• /
• 1991

The purpose of this study was to find out problems which occured between clothes and motor ability traits of the hemiplegic aged. The samples were 32 hemiplegic aged men and were compared with 43 healthy aged men. Motor ability of the samples were measured by ROM test, muscle power test and finger function test(grip strength, hand's coordination, lateral pinch, 3pt. pinch). Design of the clothes consisted of 25 variables and the analysis of dressing and undressing motion consist of 10 motions of dressing and undressing dress shirts and 8 motions of trousers. The results were as follows: 1. There were significant relationship between ROM and muscle power and finger function of the hemiplegic aged(P<.001). 2. There were significant differences between the nomal side's finger function of the hemiplegic aged and that of the healthy group(P<.001). 3. The designs of clothes such as tutle neck line, long sleeve, button cuffs, fastening lace, open zipper and belt of trousers gave much difficulty to the hemiplegic when dressing and undressing. 4. The most difficult motion of dressing and undressing was fastening when dressing both dress shirts and trousers. 5. There were partly significant relationship between design of clothes and ROM, muscle power, finger function of hemiplegic aged man. 6. There were partly significant relationship between the degree of difficulty in dressing and undressing motions and ROM, muscle power, finger function of hemiplegic aged man.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
• /
• 2007.05a
• /
• pp.41-45
• /
• 2007

Palo Verde Unit 1 nuclear power station which is located in Arizona, USA had been operating at reduced power levels around 25% since December 25, 2005 due to vibration in one of its shutdown cooling lines. During an outage from March 18, 2006 to July 7, 2006 the necessary work and modifications to remedy the situation were performed. It cost approximately $46million to buy electricity to replace that lost as a result of this event. Therefore in this study, the vibration of shutdown cooling lines in the same nuclear power plant in Korea as Palo Verde Unit 1 should be measured by the operating condition of power plant. And it was evaluated using the expression for allowable velocity in ASME OM-S/G-2003. From the result of this study it is evaluated whether it is safe or not. If not the countermeasure should be considered in this study.

• Nuclear Engineering and Technology
• /
• v.41 no.4
• /
• pp.447-454
• /
• 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.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.10a
• /
• pp.117-122
• /
• 1995

An Integrated Test Facility(ITF) is a human factors experimental environment to evaluate an advanced man machine interface(MMI) design. The ITF includes a human machine simulator(HMS) comprised of a nuclear power plant function simulator, man-machine interface, experiment control station for the experiment control and design, human behavioural data measurement system, and data analysis and experiment evaluation supporting system(DAEXESS). The most important features of ITF is to secure the flexibility and expandibility of Man Machine Interlace(MMI) design to change easily the environment of experiments to accomplish the experiment's objects In this paper, we describe a development scope and characteristics of the ITF such as, hardware and software development scope and characteristics, system thermohydraulic modelling characteristics, and experiment station characteristics for the experiment variables design and control, to be used as an experiment environment for the evaluation of VDU-based control room.

• Proceedings of the KIEE Conference
• /
• 2006.11a
• /
• pp.49-50
• /
• 2006

최근 국내 전력산업의 환경 변화는 시장참여자들의 설비투자 정책에 새로운 변화를 요구하고 있다. 시장 내 경쟁이 심화됨에 따라 경영자원의 효율성 측면에서 설비투자의 경제성에 관심이 점차 증대되고 있다. 본 논문에서는 이에 대한 해결책으로서 금융산업에서 널리 이용되고 있는 자산관리(Asset Management) 개념을 배전 설비투자 분야에 적용하기 위한 개념적 체계를 소개하고자 한다.

• KEPCO Journal on Electric Power and Energy
• /
• v.1 no.1
• /
• pp.99-104
• /
• 2015

In this study, it has been initiated to investigate the specific abnormal vibration signal that has been captured in the power equipment. Array Microphone can be used in order to detect the direction and the position of the noise source. It is possible to track the abnormal mechanical noise in the power plant by utilizing the program and the microphone array system developed from this research. Array microphone system can be operated as a constant monitoring system.

• Proceedings of the KIEE Conference
• /
• 2007.07a
• /
• pp.427-428
• /
• 2007

This paper presents a study for the Korea power system at yearly peak load time in 2007 summer period. The power system become more complex due to the gradual increment of power demand. We analyze various problems in power system operation, by the use of PSS/E(power flow, fault and transient stability study) and VSAT for voltage stability. The results of power system operating plans and countermeasures are described.