• Nuclear Engineering and Technology
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• 제54권7호
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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.

• 전기학회논문지
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• 제60권5호
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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.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1993년도 하계학술대회 논문집 A
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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.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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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.

• 한국정밀공학회지
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• 제28권2호
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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.

• 한국방사선학회논문지
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• 제11권1호
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• pp.19-25
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• 2017

본 연구는 부산광역시 거주민을 대상으로 원전주변 갑상선암 논란에 따른 원자력에 대한 전반적 인식을 분석하기 위해 위험도, 발전방식에 대한 선호도 및 경제성, 사전-사후 원자력에 대한 인식 등을 조사하였다. 그 결과, 원전 주변 갑상선암 논란을 계기로 국민들의 원자력에 대한 인식에 변화가 있는 것으로 나타났으며, 특히 사건 이전과 비교하여 위험성 요인에서 가장 큰 폭의 상승을 보였다(p<0.05). 이러한 원자력 위험성에 대한 부정적 인식은 집단의 차이에 의해 다르게 표출되는 것으로 분석되었다. 이는 과학적이고 객관적인 근거에 입각하기보다는 개인마다 상이한 선행경험이나 다른 사람과의 상호작용을 통해 획득한 정보에 기인하는 것으로 판단된다. 향후 국민들의 수준을 고려한 원자력 정책을 수립하기 위해서는 국민들의 원자력에 대한 태도와 견해를 이해하려는 노력과 무엇보다도 원자력에 대한 과학적 신뢰가 보장되어야 할 것으로 사료된다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2014년도 추계학술대회 논문집
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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.

• 한국건설관리학회논문집
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• 제18권1호
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• pp.48-57
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• 2017

1971년 우리나라 최초의 원자력발전소인 고리 1호기가 착공되어 2015년 현재 24기가 가동 중에 있으며 4기가 건설 중으로 약 40여 년간의 원자력발전소 건설 역사 동안 원전 건설의 성공적인 시공을 위한 CSFs 도출에 관한 연구는 아주 미흡한 실정이다. 본 연구에서는 시공단계에서 원전 건설의 성공적인 시공을 위한 CSFs를 도출하기 위하여 기존 연구에서 제안된 원전 및 일반 건설의 성공요인과 고찰한 원전 건설의 시공요인을 바탕으로 원전 전문가와 포커스 그룹 인터뷰를 실시하여 원전 건설의 성공적인 시공을 위한 CSFs를 도출하였다. 포커스 그룹 인터뷰 결과의 검증을 위하여 현재 원전 건설 프로젝트에 참여하고 있는6 14명의 실무 전문가들의 설문조사를 통해 도출한 CSFs의 유용성을 검증하였다. 설문 결과 분석을 통해 합리적인 공사비산정기준 수립, 원전 건설경험 인력 관리시스템 구축 및 활용, 경쟁력 있는 우수 협력업체 발굴 및 육성 방안 마련 및 검사 절차 개선 등으로 작업 대기시간의 최소화 방안 등에 대해 우선 검토 및 개선이 이루어져야 함을 도출 하였다.

• 한국방사선학회논문지
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• 제10권8호
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• pp.583-590
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• 2016

본 연구는 부산광역시 거주민을 대상으로 원전주변 갑상선암 피해 소송 이후 원자력발전소 인근지역과 시내권에 거주하는 주민간의 인식 차이를 분석하여 국민들의 원자력에 대한 수용성 수준을 판별하고자 하였다. 설문조사는 총 551명(원전인근지역 269명, 시내권 282명)을 대상으로 대인면접을 통해 이루어졌으며, 분석 결과, 원전 주변 갑상선암 발병 피해 소송 사건을 계기로 국민들의 원자력에 대한 인식에 변화가 있는 것으로 나타났다. 원전인근지역 주민의 경우 사건 이후 원자력에 대한 불신과 불안감이 높아져, 원자력에 대한 부정적 인식이 강해졌음을 확인할 수 있었다. 반면 시내권 주민들은 원전 주변 갑상선암 발병 피해 소송 사건에도 불구하고 사건 이전보다 더욱 원자력 수용성에 긍정적인 인식을 갖는 것으로 분석되었다. 그러나 원자력 안전성과 신뢰성에 대한 인식은 부정적인 것으로 분석되어 원자력 수용성과 상반되는 이중적인 인식을 보였다. 이는 부산광역시 시내권 주민들의 경우 원자력의 편익, 필요성 등을 원칙적으로 인정하나 안전성에 대해서는 의심하는 것으로 판단되며 향후 원자력의 이용 확대를 지속적으로 추진하기 위해서는 국민의 올바른 이해와 신뢰 그리고 무엇보다 국민 또는 원전인근지역 주민들과 충분한 의사소통이 필요하다고 사료된다.

• 국제학술발표논문집
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• The 7th International Conference on Construction Engineering and Project Management Summit Forum on Sustainable Construction and Management
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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.