• The Transactions of The Korean Institute of Electrical Engineers
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• v.57 no.5
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• pp.767-772
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• 2008

Korea Electric Power Research Institute in charge of the power IT project "Development of Prototype for Advanced Substation Automation System based on the Digital Control Technology", is performing the verification of performance of the substation automation system. In order to verify a system based BUS protection IED, the standardized document and procedures are required. But there is nothing to describe systematically how to verify IEC 61850 based IED in the system environment except an individual IED testing way and report. This paper presents the substation automation system based ways and procedures to verify the IED using UML(Unified Modelling Language).

• Korean Journal of Child Studies
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• v.5
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• pp.3-20
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• 1984

The purpose of this paper was to review critiques on methodological problems relating to Piaget's researches in terms of its scientific nature. On the basis of review of literature, the following problems were pointed out: 1. Notwithstanding Piaget's emphasis on the scientific requirement for verification, Piaget was against the deductive method typical of scientific verification. 2. Piaget's theory was so vague that it couldn't be falsified. 3. Piaget ignored criticism of his method, and this was viewed as unscientific in the eyes of most scientists. 4. Avoiding the antecedent-consequence sequence of scientific experimentation, Piaget took the descriptive, rather than the explanative nature. 5. Piaget didn't accept individual differences in cognitive style in his research paradigm. 6. Piaget's experimental procedures looked very simple but they were too complex to understand what was happening. 7. Although Piaget's major ideas treated the child as the active constructor of reality, the child's experimental tasks were structured by experimenter. 8. Piaget's clinical method depended heavily upon language although the procedures required manipulation of objects. 9. Piaget always justified his experiments in terms of protocois selected from all the responses obtained. However, these protocols may not be the most representative responses or behaviors showing the child's cognitive structure.

• Nuclear Engineering and Technology
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• v.27 no.4
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• pp.571-581
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• 1995

The generation, verification and validation of Emergency Procedures for Nuclear Power Plant is a difficult and complex process. Atomic Energy Control Board(AECB) requires that emergency procedure and plan be produced before obtaining the Operating License, that is, detailed plans and procedures to handle emergency situations for both on-site actions and off-site actions be developed. In this report Emergency Operating Procedures Standard for Canadian Nuclear Utilities which makes reference to U. S. practices and the current direction of emergency procedures for CAN-DU reactors are reviewed and compared based on scope(events covered), methodology (event-oriented or symptom-oriented or hybrid) and format(method of presentation) preponderantly, and an attempt is made to integrate these procedures and as a result the recommended strategy for Wolsong unit 2, 3, & 4 is presented as event-specific procedures, generic procedures(when event is not diagnosed) and whose format is combination of logic diagram and text.

• 대한공업교육학회지
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• v.40 no.1
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• pp.64-86
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• 2015

The objective of this study is to develop NCS-based vocational curriculum procedures developing models recognized by experts in the National Skill Standards and to verify them. As for a research method for efficiently achieving this study, Delphi research has been conducted three times based on the result of preliminary Delphi investigation, contents of in-depth interview (review and advice), and consideration of previous studies and literature research related to NCS in Korea and abroad. Major results of study in regard of validation of NCS-based vocational curriculum procedures developing models recognized by experts of National Skill Standards are as follows. First, validity of conceptual model(plan) of NCS-based vocational curriculum developing procedures was verified. According to the result of implementing it on 10 members of verification for Delphi preliminary investigation tools, the average was higher than 4.70, and validity of contents was turned out to be outstanding in 1.00. Secondly, validity of conceptual model(plan) of NCS-based vocational curriculum developing procedures was verified by using Delphi preliminary investigation tools. According to the result of verifying it in order on 10 members of verification for Delphi preliminary investigation tools, validity of contents on questions in each area from the development procedures model(plan) was all 1.00, and appropriateness of contents on the components was turned out to be outstanding in 1.00. In addition, validity of contents on interrelation and comprehensiveness of components in the development procedures model(plan) was all turned out to be very satisfying in 1.00. Third, Delphi investigation was implemented in three rounds on 26 Delphi panel members for the verification. As a result consistency rate of interrelation and comprehensiveness among questions in each area of development procedures model(plan), components on the contents, and elements was turned out to be outstanding in .75 from all of three rounds. Here, consistency rate from all three rounds was turned out to be 1.00, and convergence rate was shown to be .00 that very well satisfied the conditions(except for 1 question out of 29). Therefore, it was confirmed that opinion from Delphi panel members was completely consistent in the third round of Delphi investigation research. Such a result in the study was from how Delphi selection criteria were strictly reinforced, and, at the same time, implies how will of participation of Delphi panel members was important.

• Computers and Concrete
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• v.2 no.1
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• pp.31-53
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• 2005

In the present structural codes the safety verification is based on a linear analysis of the structure and the satisfaction of ultimate and serviceability limit states, using a semi-probabilistic security format through the consideration of partial safety factors, which affect the action values and the characteristic values of the material properties. In this context, if a non-linear structural analysis is wanted a difficulty arises, because the global safety coefficient, which could be obtained in a straightforward way from the non-linear analysis, is not directly relatable to the different safety coefficient values usually used for the different materials, as is the case for reinforced concrete structures. The work here presented aims to overcome this difficulty by proposing a methodology that generalises the format of safety verification based on partial safety factors, well established in structural codes within the scope of linear analysis, for cases where non-linear analysis is needed. The methodology preserves the principal assumptions made in the codes as well as a reasonable simplicity in its use, including a realistic definition of the material properties and the structural behaviour, and it is based on the evaluation of a global safety coefficient. Some examples are presented aiming to clarify and synthesise all the options that were taken in the application of the proposed methodology, namely how to transpose the force distributions obtained with a non-linear analysis into design force distributions. One of the most important features of the proposed methodology, the ability for comparing the simplified procedures for second order effects evaluation prescribed in the structural codes, is also presented in a simple and systematic way. The potential of the methodology for the development and assessment of alternative and more accurate procedures to those already established in codes of practice, where non-linear effects must be considered, is also indicated.

• Journal of the Korean Society of Systems Engineering
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• v.5 no.2
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• pp.11-16
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• 2009

This study introduces the verification, validation & accreditation (VV&A) process for modeling & simulation (M&S). VV&A is standard process for credibility of M&S. In several countries including USA, for weapon system of Defense Development using M&S, VV&A is necessary procedures to acquire official approving for credibility of M&S. Many countries have regular recommend practice guide (RPG) and instructive for VV&A of M&S. In this study, we focus the VV&A key concepts as Department of Defense RPG of USA and give the outline of the main VV&A concepts because we don't have any available VV&A Instructive. Also, this report documents the first significant VV&A application for a MITS(M-SAM Integrate Test System) including Verification and Validation(V&V) activity and tasks.

• Journal of the Ergonomics Society of Korea
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• v.18 no.3
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• pp.153-169
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• 1999

The design of nuclear control room is advancing toward totally computer based human system interfaces (HSI). Computer based interfaces offer the opportunity to provide improved support of operator performance, but if not properly deployed, can introduce new challenges. This paper reviews the Westinghouse AP-600 Human Factors Verification and Validation Plan selected for HSI evaluation model of Korea next generation nuclear control rooms. The AP-600 HSI evaluation model addressed 15 evaluation issues considering major activity class of operator and task complexity factors. This paper also describes the test procedures experimenters should follow to evaluate the addressed issues.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.28 no.5
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• pp.593-602
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• 2004

We have developed a digital control rod control system not only to improve its performance but also to improve its reliability and speed of response so that it can replace the old fashioned analog system. However, a new developed digital control system should be tested to prove the validity by using any prototype or mock-up before application. The reliability prediction and the reliability block diagram analysis methods were adopted to verify the reliability of the developed hardware. For the case of software, especially fur a new developed control algorithm it has been tested to prove performances and validation by using a dynamic simulator and mock-up of control rod drive mechanism altogether. Here we want to present some key factors regarding to the new developed digital system with some verification procedures.

• Journal of Korean Tunnelling and Underground Space Association
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• v.24 no.5
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• pp.411-429
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• 2022

Instrumentations are essential in NATM tunnels, however measuring instruments are installed and applied without performance verification procedures due to insufficient research on methods, procedures, regulations, etc. to verify the reliability of the measuring instruments. In this study, domestic and foreign regulations relating to the verification and calibration of instruments were investigated and necessities for accreditation standards were proposed. In order to identify the causes of the defects, an external inspection was performed on rock bolt stressmeter and rod extensometer, which are measuring instruments with relatively complex structures. For verifying the performance of these instruments, verification devices were developed that can load step-by-step and the causes of defects were identified in measuring instruments of nine domestic manufacturers. Through the performance test, a number of measuring instruments were found to be defective. It was important to test the performance of the instruments in the state of a finished product and accordingly performance inspection methods and procedures were proposed. The results of this study are expected to help preparing related regulations for verifying instrument performance and selecting instruments in the field.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2000.04a
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• pp.3-16
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• 2000

The ultimate safety-goal of nuclear power plants should be targeted at preventing release of nuclear radiation compared to general structures, Accordingly the phases of siting design construction and operation of NPPs are severely regulated by codes of aseismic design so as to assure safety of NPPs. To accomplish this goal strict quality assurace and seismic qualification tests should be conducted for all phases of NPP construction. In addition seismic monitoring systems should be installed and always in operation to provide proper post-earhquake procedures. Besides periodic safety review should be performed during operation along with the seismic margin assessment. In this paper general procedures to secure seismic safety of NPPs are systematically reviewed and additional considerations for improvement are suggested.