• Nuclear Engineering and Technology
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• v.54 no.7
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• pp.2519-2528
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• 2022

The child pick-up behavior of parents during an emergency can cause heavy traffic congestion and failing to evacuate an affected area successfully. In this study, we analyzed the effect of child pick-up behavior using, as an example, a nuclear power plant accident caused by an earthquake, which is a typical no-notice emergency. A quake was assumed to occur near the Shin-Kori nuclear power plant in Ulsan, Korea, resulting in a nuclear power plant accident. An agent-based dynamic simulation model using VISSIM was employed to conduct sensitivity analyses with different child pick-up rates. The results confirmed that parents are a major cause of congestion and a vulnerable class in an emergency evacuation. The child pick-up behavior caused significant traffic congestion, and parents who pick up their children showed a higher evacuation failure rate.

• The Transactions of The Korean Institute of Electrical Engineers
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• v.60 no.5
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• pp.1017-1022
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• 2011

This paper describes the improvement of the calculation by using $6{\sigma}$ method on steam turbine simulator in a nuclear power plant. The simulator is essential to not only verification and validation of control logic but also making sure of control constants in upgrading the long time used control system into the new one. And the dynamic model is a key point in that simulator. The model used during the retrofit period of the turbine controller in Kori Nuclear Power Plant makes difference in calculating generator output and control valve positions. That is because such operating data as the main steam pressure, the main steam temperature and control valve positions of Yongkwang #3 are different from those of Kori #4. Therefore, the model parameters must be tuned by using actual operating data for the high fidelity of simulator in calculating the dynamic characteristic of the model. This paper describes that the $6{\sigma}$ method is used in improvement of precision of generator output calculation in the steam turbine model of the simulator.

• Proceedings of the KIEE Conference
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• 1993.07a
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• pp.525-528
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• 1993

KEPCO Research Center is carrying out a simulator(full scope replica type) development project for two nuclear power plants(Kori-2, Younggwang-3,4) and one fossil power plant(Poryong-3,4). In this project, we aim not only the installation of high performance simulators at the power plant sites but also the realization of self reliance of power plant simulation technology in Korea. In the course of preparing procurement specification for the 3 simulators, the present status of power plant simulation technology has been surveyed and is presented in this paper. The fidelity of simulation and the automation of simulation model production has been greatly improved due to the ever increasing computing power of today's workstations. The need and importance of the application of high fidelity simulators to the operator training is refocused since the accident at TMI Nuclear Power Plant, U.S.A.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.02a
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• pp.12-27
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• 2004

Pretreatment process consisted of submerged hollow-fiber microfiltration(HMF) membrane and spiral-wound nanofiltration(SNF) membrane has been developed by NETEC, KHNP for the purpose of improving the impurities of liquid radioactive waste before entering Selective Ion Exchange System(SIES). The lab-scale combined system was installed at Kori NPP #2 nuclear power plant and demonstration tests using actual liquid radioactive waste were carried out to verify the performance of the combined system. The submerged HMF membrane was adopted for removal of suspended solid in liquid radioactive waste and the SNF membrane was used for removal of particulate radioisotope such as, Ag-l10m and oily waste because ion exchange resin can not remove particulate radioisotopes. The liquid waste in Waste Holdup Tank (WHT) was processed with HMF and SNF membrane, and SIES. The initial SS concentration and total activity of actual waste were 38,000ppb and $1.534{\times}10_{-3}{\mu}Ci/cc$, respectively. The SS concentration and total activity of permeate were 30ppb and lower than LLD(Lower Limit of Detection), respectively.

• Journal of the Korean Society for Precision Engineering
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• v.28 no.2
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• pp.233-238
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• 2011

In piping design of nuclear power plant facilities, the load stress according to self-weight is important for design values in test run(shutdown and starting). But sometimes it needs more studies, such as seismic analysis of an earthquake of power plant area and fatigue life and stress of thermal expansion and anchor displacement in operating run. In this paper, seismic evaluations were performed to nuclear piping system of Shin-Kori NO. 3&4 being built in Pusan lately. Results of seismic analysis are evaluated on basis of KEPIC MN code. The structural integrity on RCB piping system was proved.

• Journal of the Korean Society of Radiology
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• v.11 no.1
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• pp.19-25
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• 2017

In this study, in order to analyze the general awareness of the nuclear power according to the controversy of thyroid cancer around nuclear plant, we investigated risks, preference and economics regarding type of power, and awareness of pre-post nucl ear power targeting the Busan Metropolitan residents. As a result, there has been a change in people's awareness of nuclear power as a result of the controversy thyroid cancer around nuclear plant. Especially, there was the greatest increase in the risk factors compared to before the event(p<0.05). Negative awareness of nuclear risk was shown to be expressed differently accor ding to the difference between groups. It is thought that this is due to the different prior experience of each individuals or obtained information through the interaction with others rather than on scientific and objective grounds. In order to establish a nuclear power policy considering the level of the people in the future, it seems that the efforts to understand the attitudes and opinions of people about nuclear power and above all, a scientific trust in nuclear power should be guaranteed.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.10a
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• pp.110-115
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• 2014

The nuclear power plant was launched by Kori unit 1 in 1978 years. Currently, 23 nuclear power plants have been operating in Korea since 1978 years. The localization was completed for most of the reactor facility from Hanbit(Youngkwang) unit 3&4. However, RCP(Reactor Coolant Pump) and MMIS(Man Machine Interface System) is an important technology that has been excluded from the scope of the technical transfer has been dependent on a specific overseas vendor. Recent success in RCP development through co-operation with government and industries. Developed RCP will be applied to Shin-Hanul unit 1&2 nuclear power plants. The RCP operates in high speed and high pressure condition and only rotating component in the NSSS(Nuclear Steam Supply System). Therefore, the problem of vibration has arisen caused by the hydraulic forces of the working fluid. These forces can influence on the stability characteristics for entire RCS(Reactor Coolant System) loop, and can act as significant destabilizing forces. In this study, vibration evaluation of the pump shaft of development RCP estimated under normal operation and over speed conditions. In order to predict the vibration characteristics and dynamic behavior, modal analysis, critical speed analysis and unbalance response spectrum analysis were performed.

• Korean Journal of Construction Engineering and Management
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• v.18 no.1
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• pp.48-57
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• 2017

The construction of the first nuclear power plant (Kori #1) in Korea started in 1971, Korea operates 24 nuclear power plants and is constructing 4 in 2015. During about 45 years of construction experience, insufficient studies have been investigated for the identification of critical success factors(CSFs) for nuclear power plant construction. Based on literature reviews and focus group interviews, this study presented a list of CSFs for construction of nuclear power plants. A survey for validating the results of CSFs was conducted with 164 experts. This study indicates that attentions should be placed upon the lowest price-based contract awarding policy, the need for reasonable pricing standard implementation, database development, and deployment for experienced nuclear power plant construction workers, identification and nurturing of competitive subcontractors, and minimization of lag times in construction activities.

• Journal of the Korean Society of Radiology
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• v.10 no.8
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• pp.583-590
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• 2016

The subjects in this study are the residents of Busan, analyzing the perception gap between the residents adjacent to the nuclear plant and living in town, about the lawsuit of thyroid cancer damage nearby the nuclear plant, to distinguish the citizen's acceptance level about the nuclear power. 551 people(269 people adjacent to nuclear plant, 282 people in town) were face-to-face surveyed and the result showed that people's perceptions of the nuclear power has changed after the thyroid cancer damage lawsuit. In the case of the residents adjacent to the nuclear plant, it became clear that the negative perception of nuclear power became stronger due to increasing distrust and anxiety about nuclear power after the lawsuit of thyroid cancer damage nearby the nuclear plant. On the other hand, people living in town showed their positive perceptions of nuclear power despite the thyroid cancer damage lawsuit. However, two-sided perception was shown compared to the acceptance of nuclear power, since the safety and reliability of the nuclear power was analyzed as negative perception. Therefore, for the constant increased use of nuclear power in the future, national understanding and credibility, including the communication with the nation or the residents in the neighboring area of nuclear power plant, will be necessary.

• International conference on construction engineering and project management
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• 2017.10a
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• pp.8-13
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• 2017

Nuclear power plant (NPP) constructions are large scale projects that are executed for several years, and schedule control utilizing various schedules is a critically important factor. Recently Korea independently developed the Advanced Power Reactor (APR) 1400 and is building nuclear facilities applying this new reactor type. The construction of Shin-Kori NPP (SKN) Unit 3, which adopted the APR1400, was completed and commercial operation has begun, while, SKN 4, Shin-Hanul NPP (SHN) Units 1&2, and SKN 5&6 are currently under construction. Prior to the development of the APR1400, Korea built 24 reactors and accumulated the schedule data of various reactor types which provided the foundation for schedule reduction to be possible. However, as there is no schedule development and review system established based on the standard schedule data (standard activities, durations, etc.) by reactor type, the process for developing the schedule for new builds is low in efficiency consuming much time and manpower. Also all construction data has been accumulated based on schedule activities. But because the connectivity of activities between projects is low, it is difficult to utilize such accumulated data (causes for schedule delay, causes for design changes, etc.) in new build projects. Due to such reasons, issues continue to arise in the process of developing standard schedule activities and a standard schedule for nuclear power plant construction. In order to develop a standard schedule for NPP construction, i) the development of an NPP standard schedule activity list, ii) development of the connection logic of NPP standard schedule activities, iii) development of NPP standard schedule activity resources and duration, and iv) integration of schedule data need to be performed. In this paper, an analysis was made on the coherence of schedule activity descriptions of existing NPPs by applying the probabilistic methodology on activities with low connectivity due to the utilization of the numbering system of four APR1400 reactors (SHN 1&2 and SKN 3&4).This study also describes the method for developing a standard schedule activity list and connectivity measures by extracting same and/or similar schedule activities.