• Title/Summary/Keyword: Application Integrity

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A Study on the Application of Ultrasonic Testing for The Interface Integrity Evaluation between Iron and Cement of Porcelain Insulator Cap (자기애자 캡의 금구-시멘트 계면 건전성 평가를 위한 초음파법 활용에 대한 연구)

  • Yoon, Young Geun;Choi, In Hyuk;Son, Ju Am;Oh, Tae Keun
    • Journal of the Korean Society of Safety
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    • v.33 no.6
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    • pp.58-65
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    • 2018
  • The life span of the porcelain insulator was made to be 30 years, but currently many of the 154kV NGK porcelain insulators using in Korea are found to have passed the production life. Accidents caused by aged mechanical breakdown can lead to disruption of power supply in some areas, large economic losses, and casualties. Therefore, ultrasonic method, which is one of the non - destructive test methods, is applied as a method for evaluating the integrity of porcelain insulators. In this study, the experiment on the interface of cap was conducted and the difference between the energy difference and the attenuation coefficient of the reflected wave was derived according to the interface state of the steel - cement. The results of this study are expected to be used as the basic data of the ultrasonic testing to evaluate the interface condition of the porcelain insulator cap.

Application of the Leak Before Break(LBB) Concept to a Heat Exchanger in a Nuclear Power Plant

  • Kwon, Jae-Do;Lee, Choon-Yeol;Lee, Yong-Son;Sul, Il-Chan
    • Journal of Mechanical Science and Technology
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    • v.15 no.1
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    • pp.10-20
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    • 2001
  • The leak before break(LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount(approximately 37.9 liters) containing the radioactive material which can activate the radiation detector device installed in near the heat exchanger is assumed. A postulated initial flaw size that can not grow to a critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural integrity of the heat exchanger is not impeded. Particularly the informational scenario presented in this paper discusses an actual nuclear plant.

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Study on the Effective Management Plans of Mobilization Security Business which Utilizes NFC (NFC를 활용한 출동경비업무의 효율적 관리방안에 관한 연구)

  • Kim, Min Su;Lee, Dong Hwi;Kim, Kui Nam J.
    • Convergence Security Journal
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    • v.13 no.2
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    • pp.95-100
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    • 2013
  • As the near field communication technology's application scope tends to expand gradually in the various fields, application of mobile-based NFC(Near Field Communication) is increasing in the various types of technologies. The method which reads the URL address and supports access to the web site of the address if you touch the NFC device in the tag(RFID) that the URL address is stored was applied to the unmanned security system. It proposed the effective plan to manage mobilization security business in the aspects of Integrity, Damage, Real-Time, and Speed through comparison and verification of the method with the existing unmanned security system.

A simplified analysis of catenary action in steel beams in fire and implications on fire resistant design

  • Wang, Y.C.;Yin, Y.Z.
    • Steel and Composite Structures
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    • v.6 no.5
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    • pp.367-386
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    • 2006
  • This paper describes the results of a numerical investigation of the large deflection behaviour of steel beams under fire conditions, taking into consideration the effect of catenary action provided by the surrounding structures. The main focus is on the development, validation and application of a simplified calculation method that may be adopted in design calculations. Because no experimental result is available for validation of the simplified calculation method, the finite element program ABAQUS has been used to simulate the large deflection behaviour of a number of steel beams so as to provide alternative results for validation of the proposed method. Utilising catenary action has the potential of eliminating fire protection to all steel beams without causing structural failure in fire. However, practical application of catenary action will be restricted by concerns over large beam deflection causing integrity failure of the fire resistant compartment and additional cost of strengthening the connections and the surrounding structures to resist the catenary forces in the steel beams. This paper will provide a discussion on practical implications of utilising catenary action in steel beams as a means of eliminating fire protection. A number of examples will then be provided to illustrate the type of steel framed structure that could benefit the most from exploiting catenary action in fire resistant design.

A New Proposal for the Allowable Local Thickness of Straight Pipes in ASME Code Case N-597-2 (ASME 코드 케이스 N-597-2의 직관 국부허용두께의 새로운 제안)

  • Park, Jai-Hak;Shin, Kyu-In;Park, Chi-Yong;Lee, Sung-Ho
    • Journal of the Korean Society of Safety
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    • v.22 no.1 s.79
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    • pp.13-18
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    • 2007
  • Structural integrity assessment of thin-walled pipes and pipe items has become one of the major issues in the nuclear power plant. ASME Section XI Code Case N-597-2 provides a criterion for acceptance of the pipes. But the code case has several limitations for application and sometimes gives too conservative or non-conservative results. So it is necessary to understand fully the technical bases of the code case. In the code case N-597, the allowable local thicknesses of thinned straight pipes are given for three different cases. Because of the different technical base, each case gives different thickness values and sometimes gives contradictory values. In this paper attempts were made in order to propose a unified rule for the allowable local thickness and in order to remove or relax the restrictions on the application of the code case. For this purpose elastic stress analyses were made using the finite element method and the stress results were examined. Based on the obtained bending stress results, a very simple procedure was proposed to obtain the consistent allowable local thickness for the thinned straight pipes.

A Study on Dynamic Analysis of Vertical Mixed-Flow Pump for Nuclear Power Plants (원자력 발전소용 입형 사류펌프의 동적해석에 관한 연구)

  • Seo, Y.S.;Lim, W.S.;Chung, H.T.
    • Journal of Power System Engineering
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    • v.10 no.4
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    • pp.71-77
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    • 2006
  • This study introduces the seismic qualification of safety related equipments for nuclear power plants to verify the possibility of resonance in regard to the operating speed and the structural integrity due to external piping nozzle loads as well as seismic dynamic loads using El-Centro earthquake, which was occurred in the 1940's previously. As a first step, it is necessary to investigate the natural frequency of the vertical mixed flow pump in order to determine whether static or dynamic equipment comparing with seismic cut-off frequency, 33hz. Also the normal mode analysis was carried out with the introduction of seismic redesign straint at the middle of vertical pump to increase the natural frequency. In terms of structural integrity, the application of static analysis with normal, upset and faulted nozzle loads event was presented for the comparison of material allowable stress. Also the dynamic analysis was performed to show the design adequacy through the application to the case of El-Centro earthquake.

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Butt-fusing Procedures and Qualifications of High Density Polyethylene Pipe for Nuclear Power Plant Application (원자력발전소 적용 고밀도 폴리에틸렌 배관의 맞대기 융착절차 및 검증절차 분석)

  • Oh, Young-Jin;Park, Heung-Bae;Shin, Ho-Sang
    • Journal of Welding and Joining
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    • v.31 no.6
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    • pp.1-7
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    • 2013
  • In nuclear power plants, lined carbon steel pipes or PCCPs (pre-stressed concrete cylinder pipes) have been widely used for sea water transport systems. However, de-bonding of linings and oxidation of PCCP could make problems in aged NPPs (nuclear power plants). Recently at several NPPs in the United States, the PCCPs or lined carbon steel pipes of the sea water or raw water system have been replaced with HDPE (high density polyethylene) pipes, which have outstanding resistance to oxidation and seismic loading. ASME B&PV Code committee developed Code Case N-755, which describes rules for the construction of buried Safety Class 3 polyethylene pressure piping systems. Although US NRC permitted HDPE materials for Class 3 buried piping, their permission was limited to only 10-year operation because of several concerns including the quality of fusion zone of HDPE. In this study, various requirements for fusion qualification test of HDPE and some regulatory issues raised during HDPE application review in foreign NPPs are introduced.

Dynamic Material Testing of Aged Concrete Cores From the Outer Wall of the High-Flux Advanced Neutron Application Reactor

  • JaeHoon Lim;Byoungsun Park;Jongmin Lim;Yun-Young Yang;Sung-Hyo Lee;Sang Soon Cho
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.22 no.2
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    • pp.139-144
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    • 2024
  • Concrete structures must maintain their shielding abilities and structural integrity over extended operational periods. Despite the widespread use of dry storage systems for spent nuclear fuel, research on the properties of deteriorated concrete and their impact on structural performance remains limited. To address this significant research gap, static and dynamic material testing was conducted on concrete specimens carefully extracted from the outer wall of the High-flux Advanced Neutron Application ReactOr (HANARO), constructed approximately 30 years ago. Despite its age, the results reveal that the concrete maintains its structural integrity impressively well, with static compression tests indicating an average compressive strength exceeding the original design standards. Further dynamic property testing using advanced high-speed material test equipment supported these findings, showing the consistency of dynamic increase factors with those reported in previous studies. These results highlight the importance of monitoring and assessing concrete structures in nuclear facilities for long-term safety and reliability.

Development of Win32 API Message Authorization System for Windows based Application Provision Service (윈도우 기반 응용프로그램 제공 서비스를 위한 Win32 API 메시지 인가 시스템의 개발)

  • Kim, Young-Ho;Jung, Mi-Na;Won, Yong-Gwan
    • The KIPS Transactions:PartC
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    • v.11C no.1
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    • pp.47-54
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    • 2004
  • The growth of computer resource and network speed has increased requests for the use of remotely located computer systems by connecting through computer networks. This phenomenon has hoisted research activities for application service provision that uses server-based remote computing paradigm. The server-based remote computing paradigm has been developed as the ASP (Application Service Provision) model, which provides remote users through application sharing protocol to application programs. Security requirement such as confidentiality, availability, integrity should be satisfied to provide ASP service using centralized computing system. Existing Telnet or FTP service for a remote computing systems have satisfied security requirement by a simple access control to files and/or data. But windows-based centralized computing system is vulnerable to confidentiality, availability, integrity where many users use the same application program installed in the same computer. In other words, the computing system needs detailed security level for each user different from others, such that only authorized user or group of users can run some specific functional commands for the program. In this paper, we propose windows based centralized computing system that sets security policies for each user for the use of instructions of the application programs, and performs access control to the instructions based on the security policies. The system monitors all user messages which are executed through graphical user interface by the users connecting to the system. Ail Instructions, i.e. messages, for the application program are now passed to authorization process that decides if an Instruction is delivered to the application program based on the pre-defined security polices. This system can be used as security clearance for each user for the shared computing resource as well as shared application programs.

A Study on Slot Grinding for Lead Pin Punching Die (리드 핀 제조용 펀치 금형의 홈 가공에 관한 연구)

  • 이용찬;정상철;정해도
    • Journal of the Korean Society for Precision Engineering
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    • v.17 no.4
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    • pp.106-113
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    • 2000
  • One of the recent changes in machining technology is rapid application of micro- and high precision grinding processes. A fine groove generation is necessary for the fabrication of optics, electronics and semiconductor parts. Slot grinding is very efficient for the generation of micro ordered groove with hard and brittle materials. In the process of slot grinding, chipping at the sharp edges and microcracks of the ground grooves are inevitable defects. Chipping should be reduced for the improvement of surface integrity. Mechanical contact with diamond grits causes microcracks at the grooves. This damage resides subsurface, and can be the cause of failure of the punch die. This paper deals with chipping generation at the sharp edges, surface integrity of side groove and fracture strength is related to the microcracks in the slot grinding.

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