• Journal of the Korean Society for Nondestructive Testing
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• v.19 no.4
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• pp.300-313
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• 1999

비파괴검사 기술의 레벨 향상과 안정화를 통한 시간적 재현성이 있는 비파괴검사 결과의 확보를 위해서는 비파괴검사 기술자의 자격 인정 및 인증(nondestructive testing qualification and certification of personnel)제도의 확립이 매우 중요하다. 비파괴검사 결과에 대한 유효성은 비파괴검사을 실시하는 사람의 능력이나 비파괴검사에 대한 책임을 지고 있는 사람의 능력에 크게 의존한다. 1974년부터 원자력 선진국들이 중심이 되어 수행된 PISC 프로그램(program for inspection of steel components) 및 EPRI 등에서는 순회시험 (piping inspection round-robin: PIRR trial) 결과 기존 비파괴검사 방법은 모의 시험편에 있는 상당히 큰 결함도 탐지하지 못하거나 정확한 결함크기를 측정하는데 실패한 경우가 있으며, 검사자의 기량 또는 신체조건에 상당한 차이가 있는 것으로 나타났다[1]. 국제표준화기구(ISO)의 비파괴검사 기술자의 기량인정 및 인증에 대한 국제규격안 DIS(draft international standard) 9712에서는 비파괴검사를 기획 실시 감독 감시 평가를 하기 위한 적절한 이론적 및 실무적 지식을 필요로 하는 기술자의 능력을 평가하고, 문서화하는 방법을 제공하는 절차를 제시하고 있다. 국제표준화기구에 의한 비파괴검사 기술자의 기량인정 및 인증에 대한 국제통합을 추진하는 동기는 제 3자에 의한 체계적인 인증시스템을 가지고 있지 않은 나라와 새로운 NDT 방법에 대해서 인증제도를 적용할 때 세계적인 공통성을 갖도록 유도하기 위함이다. 현재, 우리나라 비파괴검사 기술자의 기술자격 인증제도는 국가기술자격법에 의거하여 한국산업인력공단에서 주관하여 기술사, 기사, 산업기사, 기능사로 구분하여 실시하고 있다. 국제표준화기구의 비파괴검사 기술자의 자격과 인증에 대한 국제 통합화(안)[2]이 거의 마무리 단계에 있고 일본을 비롯한 많은 나라가 국제규격을 기초로 한 새로운 인증제도를 발족시켜 거의 시행 단계에 있다. 반면 국내에서는 한국비파괴검사학회(KSNT)에서 비파괴검사 기술자의 자격인정 및 인증제도의 개선방향이 제시된 바 있고 [3], 표준화위원회에서 나름대로 준비를 하고 있으나 아직 구체적인 실천단계에와 있지 못하다. 본 고에서는 최근 대폭수정 보완된 ISO/DIS 9712 국제규격(안)을 회원들에게 소개하고, 우리나라의 향후 대응방안에 관한 회원 여러분의 의견 수렴에 도움을 주고자 ISO/DIS 9712(1997)를 번역하여 제공한다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.20 no.6
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• pp.1798-1809
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• 1996

The purpose of this paper is to develop new Z-Factors to evaluate the behavior of circumferential surface crack in ferritic steel piping including base metal and Submerged Arc Weld(SAW) metal in nuclear power plant. The Z-factor is a load multiplier to convert plastic load to elasto-plastic load. However the current Z-Factor is a load multiplier to convert plastic load to elasto-plastic load. However the current Z-Factor gives too conservative results. In this study, a J-estimation method, SC.TNP method, which is based on GE/EPRI expression, is used to develop new Z-Factors. The desirabilities of both the SC.TNP mehtod and the new Z-Factors are examined using the previous experimental results for the circumferential surface crack in ferritic steel pippings. The results are as follows ; (1) The SC.TNP mehtod is good for describing the circumferential surface crack behavior in farritic steel pipings, while the well-known R6 mehtod and DPFAD method give too conservative results. (2) The ASME-Z-Factor method using nwe Z-Factors well predicts the behavior of circumferential surface crack in ferritic steel pipings including base emtal and SAW metal.

• The Transactions of the Korea Information Processing Society
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• v.7 no.12
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• pp.3910-3922
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• 2000

Current power systems are distributed geographically and operated in the form of Energy Management System(EMS)/ Supervision Control and Data Acquisition(SCADA) with the aid of computers and communications. Recently a variety of utilities have had interests in using inforrration technology to bring the efficiency and low operational costs. There is also a trend to integrdte the production, transmission, distribution and management/control of power into one and unified distributed system. To this end, Electric Power Hesearch Institute(EPRI) announced a new standard communication protocol called Inter-Control Center Protocol(ICCP).ICCP specifies the use of Manufacturing Message Specification(MMS) for services required by rccr in application layer and supports the communications between heterogeneous control centers. This paper presents the characteristics of MMS,ICCP and their relationship. Futherrnore, we implement the basic functional blocks of ICCP using MMS services under TCI/IP environments. Finally, we model a simple power system and apply the rccp protocol to this system in a window-based scheme, and finally show the operation and validation of this protocol.

• Proceedings of the KIEE Conference
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• 2006.11a
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• pp.323-325
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• 2006

전력계통 에너지관리시스템(EMS)을 위한 공통 정보모델(CIM:Common Information Model)은 1990년대 후반에 EPRI의 CCAPI (Control Center Application Program Interface) 연구 프로젝트에서 시작하여, 현재는 IEC의 국제표준인 IEC 61970시리즈로 등록되어 있다. 특히, CIM은 IEC61970의 Part 301, 302에 정의되어 있는 공통데이터 모델을 지칭하며, IEC61970의 Part 401${\sim}$407에 정의되어 있는 CIS (Component Interface Specification)와 더불어 EMS의 API(Application Program Interface)를 정의하는 핵심 요소이다. CIM (Common Information Model)은 전격회사의 전력 시스템 운영을 포함하여 전력회사 전반에 사용되는 주요한 객체(object)들을 나타내는 추상적 모델(abstract model)이다. 또한, CIM은 전력계통 자원을 객체 클래스들(object classes)과 속성들(attributes)로 표현하는 표준 방법을 제공함으로써, 발전분야나 배전분야와 같이 전력 계통의 운용 영역이 다른 계통들과 EMS 시스템 연계, 독립적으로 개발된 전체 EMS 시스템간의 연계, 서로 다른 판매자에 의해서 독립적으로 개발된 EMS 응용 프로그램간의 통합을 용이하게 한다. 본 논문에서는 전력계통 공통 데이터 모델인 IEC 61970을 소개하고, 이에 기반을 둔 한국형 EMS 데이터베스 구축에 관해 설명한다.

• 제어로봇시스템학회:학술대회논문집
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• 2005.06a
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• pp.1439-1444
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• 2005

Induction motors are the most commonly used electrical drives because they are rugged, mechanically simple, adaptable to widely different operating conditions, and simple to control. The most common faults in squirrel-cage induction motors are bearing, stator and rotor faults. Surveys conducted by the IEEE and EPRI show that the most common fault in induction motor is bearing failure (${\sim}$40% of failure). Thence, this paper addresses experimental results for diagnosing faults with different rolling element bearing damage via motor current spectral analysis. Rolling element bearings generally consist of two rings, an inner and outer, between which a set of balls or rollers rotate in raceways. We set the experimental test bed to detect the rolling-element bearing misalignment of 3 type induction motors with normal condition bearing system, shaft deflection system by external force and a hole drilled through the outer race of the shaft end bearing of the four pole test motor. This paper takes the initial step of investigating the efficacy of current monitoring for bearing fault detection by incipient bearing failure. The failure modes are reviewed and the characteristics of bearing frequency associated with the physical construction of the bearings are defined. The effects on the stator current spectrum are described and related frequencies are also determined. This is an important result in the formulation of a fault detection scheme that monitors the stator currents. We utilized the FFT, Wavelet analysis and averaging signal pattern by inner product tool to analyze stator current components. The test results clearly illustrate that the stator signature can be used to identify the presence of a bearing fault.

• Corrosion Science and Technology
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• v.14 no.1
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• pp.12-18
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• 2015

Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.).

• The Journal of Korean Academy of Prosthodontics
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• v.38 no.4
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• pp.472-483
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• 2000

Before impression making in the fixed restorations or other prosthesis, hemostatic solutions are used for hemostasis and moisture control. Hemostatic solutions effectively control bleeding but their major ingredients, acid removes smear layers which are formed in the tooth preparation, exposes the dentinal tubular orifices which are occluded by smear layers, makes dentinal tubular fluid displace more easily to the various external stimulus, and according to the hydrodynamic theory, consequently causes dentin hypersensitivity. To know the effect of hemostatic solutions on dentin permeability, coronal dentin discs, 1mm in thickness, were prepared from extracted third molars free from decay and wear, and a split chamber device was used. Hydraulic conductance values and SEMs, which were measured before and after treatment with $Astringedentr^{(R)},\;Altract^(R)\;and\;Epri-dent^{(R)}$, were compared and ana-lysed. The following conclusions were drawn: 1. Hydraulic conductance values which were measured after the treatment of hemostatic solutions were increased in all groups(p<0.05). 2. %change values of hydraulic conductance were compared but no significant difference was found among the three hemostatic solutions(p<0.05). 3. On SEM observations of all groups, after treatment smear layers were removed and dentinal tubular orifices were partially exposed. On the basis of these conclusions, the reckless use of hemostatic solutions should be restricted, and when in use, various methods should be considered to protect dentin.

• Nuclear Engineering and Technology
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• v.48 no.1
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• pp.16-25
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• 2016

In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconiumalloy fuel claddingmaterials are rapidlyheateddue to nuclear decay heating and rapid exothermic oxidation of zirconium with steam. This heating causes the cladding to rapidly react with steam, lose strength, burst or collapse, and generate large quantities of hydrogen gas. Although maintaining core cooling remains the highest priority in accident management, an accident tolerant fuel (ATF) design may extend coping and recovery time for operators to restore emergency power, and cooling, and achieve safe shutdown. An ATF is required to possess high resistance to steam oxidation to reduce hydrogen generation and sufficient mechanical strength to maintain fuel rod integrity and core coolability. The initiative undertaken by Electric Power Research Institute (EPRI) is to demonstrate the feasibility of developing an ATF cladding with capability to maintain its integrity in $1,200-1,500^{\circ}C$ steam for at least 24 hours. This ATF cladding utilizes thin-walled Mo-alloys coated with oxidation-resistant surface layers. The basic design consists of a thin-walled Mo alloy structural tube with a metallurgically bonded, oxidation-resistant outer layer. Two options are being investigated: a commercially available iron, chromium, and aluminum alloy with excellent high temperature oxidation resistance, and a Zr alloy with demonstratedcorrosionresistance.Asthese composite claddings will incorporate either no Zr, or thin Zr outer layers, hydrogen generation under severe LOCA conditions will be greatly reduced. Key technical challenges and uncertainties specific to Moalloy fuel cladding include: economic core design, industrial scale fabricability, radiation embrittlement, and corrosion and oxidation resistance during normal operation, transients, and severe accidents. Progress in each aspect has been made and key results are discussed in this document. In addition to assisting plants in meeting Light Water Reactor (LWR) challenges, accident-tolerant Mo-based cladding technologies are expected to be applicable for use in high-temperature helium and molten salt reactor designs, as well as nonnuclear high temperature applications.

• Journal of Energy Engineering
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• v.23 no.2
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• pp.183-190
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• 2014

A Commercial Grade Item Dedication(CGID) for Korean operating nuclear power plants has been implemented since 2012. The CGID implementation and strategies for Korea are established as follows: CGID policy establishment, R&D of a specific methodologies of CGID, enrollment of third party organizations for CGID work, CGID program establishment for enrolled suppliers, establishment of training courses for certification, and CGID process development for quality class Q and A. Consequently, it is expected that these activities are enable to enhance the reliability and the safety of components and/or parts in nuclear power plants.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.10 no.9
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• pp.2236-2245
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• 2009

This paper proposes the process for evaluating the impact of charging the PHEV(Plug-In Hybrid Electric Vehicle) on the distribution systems, and analyzes the study results employing the actual systems as the PHEV is highly expected to increase in the automobile industries in North America in the near future. Since the charging load of the PHEV directly connected to the distribution systems would consume electric power much more than any other existing electric product of residential customers, the new modeling and process would be required to consider the PHEV in distribution systems planning. The EPRI(Electric Power Research Institute) is collaboratively conducting the impact study of PHEV on the distribution systems with power utilities in North America. This study models distribution systems and the charging load of the PHEV using OpenDSS software, and analyzes the impact of PHEV on the distribution systems by assuming various scenarios with different charging time and PHEV types.