• Title/Summary/Keyword: Protection and Maintenance

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Development and Application of Dry Process Caisson for Maintenance of Submerged Barber Structure

  • Lee, Joong-Woo;Lee, Seung-Chul;Oh, Dong-Hoon;Kwak, Seung-Kyu;Lee, Jeong-Su
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2006.10a
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    • pp.105-114
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    • 2006
  • Together with the trend of enhancement in domestic industrial development and economic progress due to import and export, the demand for construction of the roads, bridges, especially port facilities, and several coastal protection and ocean structures is increasing rapidly. MOMAF of Korean Government is driving construction of 9 new ports and renovation of the existing fishery ports. Among these structures most of bridge base, wharves, dolphins, quays, and jetties are being newly built of steel or concrete pile. As the base, supporting bulkheads, and piles are underwater after construction, it is difficult to figure out the status of structures and not enough to get maintenance and strengthen the structures. Every year, moreover, these works suck the government budget due to higher incomplete maintenance expense for protection from corrosions of structures and increased underwater construction period. for the purpose of cutting down the government budget, it is necessary to extend the life cycle of the existing structures. We developed a new method for maintenance of submerged structures near the waterline by allowing dry work environment with the floating caisson. The method shows easy to move around the working area and handle. It also showed not only a significant reduction of maintenance expenses and time for anti-corrosion work but also better protection. This will be a milestone to reduce the maintenance and construction expenses for the shore and water structures.

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Study on the Corrosionproofing in Concrete by Cathodic Protection (전위변화에 의한 콘크리트내의 철근방식에 관한 연구)

  • Lim, Seo-Hyung
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.3 no.2
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    • pp.213-220
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    • 1999
  • The purpose of this study is to apply cathodic protection to reinforced concrete structure and provide fundamental data to prevent the corrosion. The theory of cathodic protection of steel in concrete is to apply sufficient direct current so that corroding anodes on the steel are prevented from discharging ions. Two methods are used to supply the external current. In one, the protected metal is the cathode by connecting it to a more active metal. In the second, an external direct current power source supplies the current. The first is the sacrificial-anode system and the second the impressed-current system. The study results showed that the corrosion of the reinforcing steel in concrete could be enormously decreased by using protective current. The sacrificial anode and concrete nave to be adhered closely each in order to prevent the corrosion of reinforcing steel.

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A investigation study on the Maintenance Management for Fire Safety According to Analysis of Fire Accident in Korea(I) (국내 지하공동구의 화재사례 분석을 통한 화재안전관리방안에 관한 조사 연구(I))

  • Kim, Dong-Eun;Shin, Yi-Chul;Kwon, Young-Jin
    • Proceedings of the Korea Institute of Fire Science and Engineering Conference
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    • 2008.11a
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    • pp.328-333
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    • 2008
  • Underground utility tunnels are important facilities not only as an essential social infrastructure for modern information society but as the economic and efficient carrier of various urban infrastructure including electric power lines, communication cables, gas pipes, water supply and drainage pipes and energy supplies to metropolitan and residential areas. It is the aim of this study to investigation study on the Maintenance Management for Fire Safety According to Analysis of Fire Accident in Korea.

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Long-term Radiation Dose Reduction Plan of KHNP

  • Kim, Saeng-Ki;Shin, Sang-Woon;Lim, Byoung-Chan
    • Journal of Radiation Protection and Research
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    • v.28 no.2
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    • pp.137-143
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    • 2003
  • Annual radiation dose limit to radiation worker was substantially lowered in Korea by the adoption of 1990 recommendations of the International Commission on Radiation Protection (ICRP 60) in its legislation. On the other hand, radiation management environment in nuclear power plants is getting more worse because of the accumulation of radiation sources inside the system and the frequent need for maintenance according as the operation years of nuclear power plants increase. Therefore, Korea Hydro & Nuclear power Co., Ltd. (KHNP) has established a long-term 10 years plan from 2001 to 2010 for the reduction of radiation dose to workers. The plan is aimed for the reduction of annual dose per unit averaged over 5 years from 0.9 man-Sv in 2001 to 0.75 man-Sv in 2010 by radiation source reduction, equipment/tool improvement or new equipment development for easy maintenance, and the improvement of administration and system.

Radiation Exposure Reduction in APR1400

  • Bae, C.J.;Hwang, H.R.;Matteson, D.M.
    • Journal of Radiation Protection and Research
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    • v.28 no.2
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    • pp.127-135
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    • 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.

Optimization of preventive maintenance of nuclear safety-class DCS based on reliability modeling

  • Peng, Hao;Wang, Yuanbing;Zhang, Xu;Hu, Qingren;Xu, Biao
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3595-3603
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    • 2022
  • Nuclear safety-class DCS is used for nuclear reactor protection function, which is one of the key facilities to ensure nuclear power plant safety, the maintenance for DCS to keep system in a high reliability is significant. In this paper, Nuclear safety-class DCS system developed by the Nuclear Power Institute of China is investigated, the model of reliability estimation considering nuclear power plant emergency trip control process is carried out using Markov transfer process. According to the System-Subgroup-Module hierarchical iteration calculation, the evolution curve of failure probability is established, and the preventive maintenance optimization strategy is constructed combining reliability numerical calculation and periodic overhaul interval of nuclear power plant, which could provide a quantitative basis for the maintenance decision of DCS system.

A Study on Investigation into Actual Condition of Management in Fire Protection System -Apartment Buildings, Shopping Center, Office Buildings- (소방시설 관리실태조사에 관한 연구 -공동주택, 상가건축물, 사무소건축물-)

  • 김홍배;한상민;이영재;조병선
    • Fire Science and Engineering
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    • v.15 no.3
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    • pp.70-76
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    • 2001
  • In a daily life these days, the safety and the comfort are considered very important. As the same as other areas, the good maintenance of fire protection systems and the fire drill plans in buildings can minimize the loss of human life and the property in case of fires. In this paper, a survey has been conducted to investigate the maintenance status of the fire protection systems of apartment buildings, shopping center and office buildings. Both practical procedures for checking the systems and for fire drills and strategic plans to minimize the losses in case of fires are suggested by analyzing how well the occupants in the buildings acknowledge the evacuation drills when the fire occurs.

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A development of digital motor protection relay for power supervisory control system (전력감시 제어시스템을 위한 모터보호용 디지탈 보호계전기 개발)

  • 이성환;우천희;정현호;김정한;김상철
    • 제어로봇시스템학회:학술대회논문집
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    • 1997.10a
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    • pp.1496-1499
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    • 1997
  • Recently the major requirements have emerged in industrial substation system field. One is the simple arrangement of main power supply equipment and the other is the introduction of highly computer-controlled system for operation, maintenance and protection. This paper deals with the systems including motor-type relay systems, supervisory and control systems, digital type relay protectiion systems.

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