• Journal of the Korea Academia-Industrial cooperation Society
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• v.16 no.12
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• pp.8462-8471
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• 2015

It is widely known that consumer satisfaction, as well as consumer voice and loyalty, affect firms' performance. Prior studies on consumer satisfaction have focused on expectancy disconfirmation theory and its effects on satisfaction related to disconfirmation with consumer expectation and with perceived performance. This study classified consumer expectation into should-expectation and will-expectation, and investigated how disconfirmation with these expectations affects consumer satisfaction differently based on regulatory focus. Specifically, for promotion-focused consumers, disconfirmation of will-expectation has a more significant influence on consumer satisfaction than that of should-expectation. For prevention-focused consumers, disconfirmation of should-expectation has a more significant influence on consumer satisfaction. The results of this study provide academic insights that not only generic expectation (will-expectation) but also should-expectation play an important role in determining consumer satisfaction according to regulatory focus. In addition, it is expected that the findings can be used as a guide to manage consumer expectation in practice.

• Proceedings of the Korean Society of Marine Engineers Conference
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• 2005.06a
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• pp.293-298
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• 2005

The following is final report for governor upgrade for PWR NPP safety related EDG Kori NPP No.2 Unit. The upgraded system includes more beneficial function like as "Slow start with starting ramp", "Generator load sensing & control capability" and "Emergency ramp during slow start". This paper show functional operation of slow start regime according to NRC regulatory guide which guide regulation to NPP safety related environment.

• Proceedings of the KIPE Conference
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• 2005.07a
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• pp.581-583
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• 2005

The paper is final report for speed control upgrade and analysis report which recently performed on PWR NPP safety related EDG KHNP Ulchin NPP No.2 Unit. The upgraded system includes more beneficial function like as 'Slow start with starting ramp', 'Generator load sensing & control capability' and 'Emergency ramp during slow start'. This paper shows functional operation of slow start regime according to NRC regulatory guide which guide regulation to NPP safety related environment.

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.25 no.9
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• pp.599-605
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• 2015

The revised U.S. Nuclear Regulatory Commission(NRC), Regulatory Guide(RG) 1.20, rev.3 requires the evaluation of the potential adverse effects from pressure fluctuations and vibrations on piping and components for the reactor coolant, steam, feedwater, and condensate systems. Detailed vibration analyses for the systems attached to the steam generator are very difficult, because these piping systems are very complicated. This paper suggests a screening method for the flow-induced vibration of acoustic resonances and pump-induced vibration of the piping systems attached to the steam generator in order to conduct the APR1400 comprehensive vibration assessment program. This paper seeks to address the areas such as potential vibration sources, and methods to prevent the occurrence of acoustic resonances and pump-induced vibration of piping systems attached to the steam generator, for conducting the APR1400 comprehensive vibration assessment program. The screening method in this paper will be used to estimate the flow-induced vibration of the piping systems attached to the steam generator for the APR1400.

• The Journal of the Korea institute of electronic communication sciences
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• v.12 no.5
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• pp.725-730
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• 2017

The use of general IT resources in the Instrumentation and Control system(I&C) for the safety of Nuclear Power Plants(NPPs) is increasing. As a result, potential security vulnerabilities of existing IT resources may cause cyber attack to NPPs, which may cause serious consequences not only to shutdown of NPPs but also to national disasters. In order to respond to this, domestic nuclear regulatory agencies are developing guidelines for regulating nuclear cyber security regulations and expanding the range of regulatory targets. However, it is necessary to take measures to cope with not only general security problems of NPPs but also attacks specific to NPPs. In this paper, we select 42 items related to the vulnerability inspection in the contents defined in R.G.5.71 and classify it into 5 types. If the vulnerability inspection tool is developed based on the proposed analysis, it will be possible to improve the inspection efficiency of the cyber security vulnerability of the NPPs.

• Korean Journal of Clinical Pharmacy
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• v.21 no.4
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• pp.339-346
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• 2011

Over the past few decades, drug regulatory agencies in advanced countries have been emphasizing pharmacometrics as a tool for an effective and efficient drug evaluation. Despite this international movement, the value of pharmacometrics is still poorly recognized by the Korean drug evaluation system. This study aimed to analyze the current state of utilization of pharmacometrics by foreign drug regulatory agencies and develop a road map to guide the implementation pharmacometrics into the Korean drug evaluation system. MEDLINE and foreign drug regulatory agency database were extensively searched to obtain scientific research articles, guidance, regulations and pharmacometric review reports on foreign pharmacometric drug evaluation system. A systematic roadmap comprised of 3 stages to implement pharmacometrics in Korean drug evaluation system was formulated after analyzing the collected data in tune with the current evaluation system. Pharmacometrics is an urgently required tool to achieve an efficient drug evaluation and review in Korea. The road map developed by this study is expected to aid in setting up a policy to implement and utilize pharmacometrics in Korea.

• Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.17 no.2
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• pp.102-108
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• 2003

This paper presents a new Data acquisition system that can improve a accuracy and response characteristics by designing a SDAS(Signal Datat Acquisition System). I&C(Instrumentation and Control) system, which it applied for Nuclear Power Plant, affects for safety either directly or indirectly. It should be assessed by the equipment qualification procedure to confirm the functionality during design life before it apply on the nuclear power plant depending on safety classification. This paper proposes data acquisition system that required as an essential measurement equipment in the method and procedure of equipment qualification following of standards and codes of IEEE and Nuclear Regulatory Guide. It provides comparable and experimental studies have been carried out. The presented results from the above investigation show considerably improved accuracy performance in the data acquisition system. This circuit will be able to be used in high performance I&C system.

• Nuclear Engineering and Technology
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• v.49 no.4
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• pp.760-768
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• 2017

The transition temperature shift (TTS) of the reactor pressure vessel materials is an important factor that determines the lifetime of a nuclear power plant. The prediction of the TTS at the end of a plant's lifespan is calculated based on the equation of Regulatory Guide 1.99 revision 2 (RG1.99/2) from the US. The fluence factor in the equation was expressed as a power function, and the exponent value was determined by the early surveillance data in the US. Recently, an advanced approach to estimate the TTS was proposed in various countries for nuclear power plants, and Korea is considering the development of a new TTS model. In this study, the TTS trend of the Korean surveillance test results was analyzed using a nonlinear regression model and a mixed-effect model based on the power function. The nonlinear regression model yielded a similar exponent as the power function in the fluence compared with RG1.99/2. The mixed-effect model had a higher value of the exponent and showed superior goodness of fit compared with the nonlinear regression model. Compared with RG1.99/2 and RG1.99/3, the mixed-effect model provided a more accurate prediction of the TTS.

• Nuclear Engineering and Technology
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• v.51 no.4
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• pp.1032-1036
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• 2019

When the equipment which is related to safety or important to power production is installed in nuclear power plant units (NPPs), verification of equipment Electromagnetic Susceptibility (EMS) must be performed. The low-frequency radiated magnetic field susceptibility (RS101) test is one of the EMS tests specified in U.S NRC (Nuclear Regulatory Commission) Regulatory Guide (RG) 1.180 revision 1. The RS101 test verifies the ability of equipment installed in close proximity to sources of large radiated magnetic fields to withstand them. However, RG 1.180 revision 1 allows for an exemption of the low-frequency radiated magnetic susceptibility (RS101) test if the safety-related equipment will not be installed in areas with strong sources of magnetic fields. There is no specific exemption criterion in RG 1.180 revision 1. EPRI TR-102323 revision 4 specifically provides a guide that the low-frequency radiated magnetic field susceptibility (RS101) test can be conservatively exempted for equipment installed at least 1 m away from the sources of large magnetic fields (>300 A/m). But there is no exemption criterion for equipment installed within 1 m of the sources of smaller magnetic fields (<300 A/m). Since some types of equipment radiating magnetic flux are often installed near safety related equipment in an electrical equipment room (EER) and main control room (MCR), the RS101 test exemption criterion needs to be reasonably defined for the cases of installation within 1 m. There is also insufficient data regarding the strength of magnetic fields that can be used in NPPs. In order to ensure confidence in the RS101 test exemption criterion, we measured the strength of low-frequency radiated magnetic fields by distance. This study is expected to provide an insight into the RS101 test exemption criterion that meets the RG 1.180 revision 1. It also provides a margin analysis that can be used to mitigate the influence of low-frequency radiated magnetic field sources in NPPs.

• Journal of Advanced Navigation Technology
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• v.17 no.4
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• pp.442-448
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• 2013

I&C (Instrumentation & Control) system is different from information system and the security design of the two systems are also different. The modeling activity is needed based on the security control guide in order to build I&C system security control. In this paper, the role and by the security control, we designed the relationship (that is, the relation schema) between the documents for 'The system for supporting the cyber security control of I&C system design' based on the security control guide. The designed schema plans 'The system for supporting the cyber security control of I&C system' for observing the security control guide, and is used as the database and content that supports its design and implementation. The process and system of the proposed schema is utilized and designed. The design of the schema and system is intensified in the design phase with the proposed mode and supporting the I&C system cyber security design.