• 한국건축시공학회:학술대회논문집
• /
• 한국건축시공학회 2012년도 추계 학술논문 발표대회
• /
• pp.205-206
• /
• 2012

In general, nuclear power plant concrete structure's performance has been very good with the majority of identified problems initiating during construction and corrected at that time. This study is experiments to improve drying shrinkage using glycol ether-based material for the durability of nuclear power plants. Thus, this study evaluated the obtained data from a mock up test for the practical use of concrete containing glycol ether. According to the results of this study, the concrete showed resistance performance of around 40% to drying shrinkage.

• 한국건축시공학회:학술대회논문집
• /
• 한국건축시공학회 2012년도 추계 학술논문 발표대회
• /
• pp.201-202
• /
• 2012

Recently, High-Strength steel reinforcement has been studied throughout the internal and external. One of the advantages using High-Strength steel reinforcement in construction is the economic effect due to the decreasing of its quantity. Also, another good effect is the increases of workability by reason of reducing the congestion. But, realistically it is not used in nuclear power plant construction site because of the restriction of design standard. The purpose of this report secures the reliability and changes the code through the performance evaluation test of the wall using the high-strength steel reinforcement in nuclear power plant.

• 비파괴검사학회지
• /
• 제30권4호
• /
• pp.317-323
• /
• 2010

원자력발전소 배관 용접부에 대한 수동 초음파검사는 KPD(Korean Performance Demonstration)의 일반 절차서를 사용하여 기량 검증을 인정받고 있으나, 자동 초음파검사의 경우에는 일반 절차서가 없으며 해당 자동 검사 장비를 이용하여 절차서 기량 검증을 받아야 한다. 현재까지 국내에서 수행되고 있는 자동 초음파검사에 대한 절차서 기량검증은 대부분 펄스-반사기법을 적용한 절차서이나, 최근에 각광받고 있는 위상배열 초음파검사 기법을 이용한 절차서 기량검증은 국내에서 시행된 사례가 전무하다. 본 연구에서는 원자력발전소 가동중검사에 위상배열 초음파검사 기법을 적용하기 위하여 위상배열 초음파 신호취득 및 평가 소프트웨어를 개발하고 위상배열 초음파 탐촉자 및 웨지를 설계 하였다. 개발된 절차서에 대하여 결함 검출, 길이 및 크기 측정에 대한 기량검증을 수행하였으며, 검증된 위상배열 초음파탐상검사 절차서는 향후 원자력발전소 배관 용접부 검사에 적용할 예정이다.

• 대한인간공학회:학술대회논문집
• /
• 대한인간공학회 1993년도 추계학술대회논문집
• /
• pp.21-30
• /
• 1993

This paper describes the development of a simulation model of nuclear power plant operators including cognitive aspects by using a network modeling soft ware, Micro-SAINT (System Analysis of Integrated Networks of Tasks) for the analysis of operator performance. Network model description based on Micro-SAINT includes tasks, resources, precedence relations among tasks, flow of information and PSFs (Performance Shaping Factors) on task performance. We have tried to evaluate the performance with several performance measures such as the number of tasks allocated, relative time presure among operators within a shift, for the selected test accident scenarior; small-break LOCA (Loss of Coolant Accident) in a PWR (Pressurized Water Reactor) type nuclear power plant.

• 한국지진공학회논문집
• /
• 제24권1호
• /
• pp.1-8
• /
• 2020

In 2016, an earthquake occurred at Gyeongju, Korea. At the Wolsong site, the observed peak ground acceleration was lower than the operating basis earthquake (OBE) level of Wolsong nuclear power plant. However, the measured spectral acceleration value exceeded the spectral acceleration of the operating-basis earthquake (OBE) level in some sections of the response spectrum, resulting in a manual shutdown of the nuclear power plant. Analysis of the response spectra shape of the Gyeongju earthquake motion showed that the high-frequency components are stronger than the response spectra shape used in nuclear power plant design. Therefore, the seismic performance evaluation of structures and equipment of nuclear power plants should be made to reflect the characteristics of site-specific earthquakes. In general, the floor response spectrum shape at the installation site or the generalized response spectrum shape is used for the seismic performance evaluation of structures and equipment. In this study, a generalized response spectrum shape is proposed for seismic performance evaluation of structures and equipment for nuclear power plants. The proposed response spectrum shape reflects the characteristics of earthquake motion in Korea through earthquake hazard analysis, and it can be applied to structures and equipment at various locations.

• 한국실내디자인학회논문집
• /
• 제19권6호
• /
• pp.249-256
• /
• 2010

For guaranteeing for security of nuclear power plant, ergonomic factors have been applied to design of main control room, core area for management and control of nuclear power plant, but design elements for performance of operators have been ignored. As the behaviors of operators are important for security of nuclear power plant, space design which makes them pleasant psychologically and makes them maintain attention on security equipments ceaselessly is required. Therefore, the purpose of this study is to analyze space characteristics of main control rooms according to regulations of nuclear power plant and general guidelines of space design, and to offer basic data for designing of main control room which makes operators pleasant psychologically and physically. At first, theoretical issues related with design of main control room are reviewed and several premises of space are developed by abstracting design elements from common space and regulations of nuclear power plant and, then integrating each design elements interactively. In short, the improvement of system environment based on human-machine interface space has brought about perceptual, cognitive, and spatial changes and has realized next generation of main control rooms. And, differences and similarities between ordinary space and main control room, which ergonomic sizes and regulations are applied and is VDT environment based on LDP, are discussed in relation to 13 design elements and 17 space premise.

• 비파괴검사학회지
• /
• 제34권5호
• /
• pp.384-389
• /
• 2014

본 논문에서는 국내 원자력발전소 초음파검사자 기량검증시험 결과를 검토하였다. 원자력발전소 안전관련 설비에 대한 초음파검사 기량검증 요건은 ASME B&PV Code Section XI 1989 겨울 부록에서 최초로 언급되었다. 한국수력원자력(주)은 ASME Code Section XI, Appendix VIII의 요건 적용을 위해 국내 원자력발전소에 적합한 한국형 초음파검사 기량검증(KPD) 시스템을 개발, 규제기관의 승인을 받아 2004년 7월부터 운영하고 있다. 본 논문에서는 2004년부터 2013년까지 수행한 초음파검사자 기량검증시험 결과의 검토 내용으로 초음파검사 결함 검출 향상 및 기량훈련시스템 연구 개발에 도움을 줄 것으로 기대한다.

• 제어로봇시스템학회논문지
• /
• 제17권11호
• /
• pp.1090-1094
• /
• 2011

The major goal of nuclear power industries during past 10 years has been increasing reliability and utility capacity factor. But as capacity factors crept upward, it became harder and harder to attain next percentage of improvement. Therefore, other innovative technologies and method are required. The monitoring, diagnostic and prognostic technologies have been applied to the fossil power plants and contributed a lot on improving their reliability and performance. However nuclear industries are still reluctant to apply the technology by several reasons. In this paper, current preventive maintenance status of nuclear power plants and industrial practice of monitoring, diagnostic and prognostic technologies are investigated. In addition, the restriction in the implementation of the technologies to the nuclear power plants are defined. Finally, we suggest appropriate methods of implementing the technology to nuclear industries for improving current reliability and performance.

• 설비공학논문집
• /
• 제24권7호
• /
• pp.591-597
• /
• 2012

For the past few years, the concern for clean energy has been greatly increased. Ocean thermal Energy Conversion(OTEC) power plants are studied as a viable option for the supply of clean energy. In this study, we examined the thermodynamic performance of the OTEC power system for the production of electric power. Computer simulation programs were developed under the same condition and various working fluids for closed Rankine cycle, regenerative cycle, Kalina cycle, open cycle, and hybrid cycle. The results show that the regenerative cycle showed the best system efficiency. And then we examined the thermodynamic performance of regenerative cycle OTEC power system using the condenser effluent from Uljin nuclear power plant instead of the surface water. The highest system efficiency of the condition was 4.55% and the highest net power was 181 MW.

• Nuclear Engineering and Technology
• /
• 제51권5호
• /
• pp.1289-1296
• /
• 2019

Non-functional requirements plays a critical role in designing variety of applications domain ranges from safety-critical systems to simple gaming applications. Performance is one of the crucial non-functional requirement, especially in control and safety systems, that validates the design. System risk can be quantified as a product of probability of system failure and severity of its impact. In this paper, we devise a technique to do the performance analysis of safety critical and control systems and to estimate performance based risk factor. The technique elaborates Petri nets to estimate performability to ensure system dependability requirements. We illustrate the technique on a case study of Nuclear Power Plant system. The technique has been validated on 17 safety critical and control systems of Nuclear Power Plant.