• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 1998년도 The Korea Society for Simulation 98 춘계학술대회 논문집
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• pp.86-90
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• 1998

The safety and reliability of nuclear power plant operations relies heavily on the plant operators ability to respond to various emergency situations. It has become standard industry practice to utilize simulators to improve the safety and reliability of nuclear power plants operations. The simulators built for Younggwang#3,4, which is the basic model of the Korean Nuclear Power Plant design, has been developed precisely for this purpose. Dynamic Model and Display Model are developed under US3(UNIX Simulation Software Support System) environment in simulator for Younggwang#3,4. Since these two models are developed under each own operating system, it is necessary to develop a method for transporting data between these two systems. This paper descirves communication environment between Dynamic Model and Display Model, and addresses a file generation method for the Display Model, which will be necessary for designing MMI of MCR(Main Control Room) in the furture.

• Nuclear Engineering and Technology
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• 제47권6호
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• pp.729-737
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• 2015

Wireless communication technologies, especially smartphones, have become increasingly common. Wireless technology is widely used in general industry and this trend is also expected to grow with the development of wireless technology. However, wireless technology is not currently applied in any domestic operating nuclear power plants (NPPs) because of the highest priority of the safety policy. Wireless technology is required in operating NPPs, however, in order to improve the emergency responses and work efficiency of the operators and maintenance personnel during its operation. The wired telephone network in domestic NPPs can be simply connected to a wireless local area network to use wireless devices. This design change can improve the ability of the operators and personnel to respond to an emergency situation by using important equipment for a safe shutdown. IEEE 802.11 smartphones (Wi-Fi standard), Internet Protocol (IP) phones, personal digital assistant (PDA) for field work, notebooks used with web cameras, and remote site monitoring tablet PCs for on-site testing may be considered as wireless devices that can be used in domestic operating NPPs. Despite its advantages, wireless technology has only been used during the overhaul period in Korean NPPs due to the electromagnetic influence of sensitive equipment and cyber security problems. This paper presents the electromagnetic verification results from major sensitive equipment after using wireless devices in domestic operating NPPs. It also provides a solution for electromagnetic interference/radio frequency interference (EMI/RFI) from portable and fixed wireless devices with a Wi-Fi communication environment within domestic NPPs.

• Nuclear Engineering and Technology
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• 제50권3호
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• pp.488-493
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• 2018

The Firebrick Resistance-Heated Energy Storage (FIRES) concept developed by the Massachusetts Institute of Technology aims to enhance profitability of the nuclear power industry in the next decades. Studies carried out at Massachusetts Institute of Technology already provide estimates of the potential revenue from FIRES system when it is applied to industrial heat supply, the likely first application. Here, we investigate the possibility of operating a power plant (PP) with a fluoride-salt-cooled high-temperature reactor and a closed Brayton cycle. This variant offers features such as enhanced nuclear safety as well as flexibility in design of the PP but also radically changes the way of operating the PP. This exploratory study provides estimates of the revenue generated by FIRES in addition to the nominal revenue of the stand-alone fluoride-salt-cooled high-temperature reactor, which are useful for defining an initial design. The electricity price data is based on the day-ahead markets of Germany/Austria and the United States (Iowa). The proposed method derives from the equation of revenue introduced in this study and involves simple computations using MatLab to compute the estimates. Results show variable economic potential depending on the host grid but stress a high profitability in both regions.

• Nuclear Engineering and Technology
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• 제43권4호
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• pp.375-382
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• 2011

The prospects for growth of the nuclear power industry in Korea have improved remarkably as the demand for energy increases in stride with economic development. Meanwhile, as nuclear energy development is enhanced, nuclear technology has also improved evolutionarily and innovatively in the areas of reactor design and safety measures. As nuclear technology development in Korea advances, more human resources are required. Accordingly, the need for a well-managed program of human resource development (HRD) aimed at assuring needed capacities, skills, and knowledge and maintaining valuable human resources through education and training in various nuclear-related fields has been recognized. A well-defined and object-oriented human resource development and management (HRD&M) is to be developed in order to balance between the dynamics of supply and demand of the workforce in the nuclear industry. The HRD&M schemes include a broad base of disciplines, education, sciences, and technologies within a framework of national sustainable development goals, which are generally considered to include economics, environment, and social concerns. In this study, the projection methodology considering a variety of economic, social, and environmental factors was developed. Using the developed methodology, medium- and long-term nuclear human resources projections up to 2030 were conducted in compliance with the national nuclear technology development programmes and plans.

• 원자력산업
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• 제19권6호통권196호
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• pp.48-55
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• 1999

원자력발전소가 안전하게 운전되기 위해서는 실제 직접 설비를 다루고 있는 발전소 운전원의 역할이 매우 중요하다. 운전원의 인적 실수를 감소시키기 위해서는 설비 개선이나 제도적인 장치도 물론 중요하지만 누구나 운전원으로 근무하기를 희망하고 자긍심을 가질 수 있는 정책적인 지원이 병행되지 않으면 근본적으로 인적 실수를 방지하는데는 한계가 있다. 따라서 인적 실수를 근본적으로 방지하기 위해서는 관리자는 주제어실내에서 운전원의 행위를 관리 감독하는 역할에 충실해야 하고 보수적인 의사 결정을 해야 한다. 그리고 우수한 인력을 운전원에 배치하고, 경험있는 운전원들이 긍지와 자부심을 가지고 되도록 오랜 기간운전원으로서 근무할 수 있는 환경을 만들어 주어야 한다.

• 원자력산업
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• 제19권6호통권196호
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• pp.36-41
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• 1999

우리 나라의 에너지 안보 정도를 정량화하여 나타낼 수 있는 에너지 안보 지수를 개발, 제시하고 이를 이용하여 원자력 발전의 도입이 국내 에너지 안보에 기여한 정도를 측정하였다. 에너지 안보에의 기여 항목으로는 에너지원 다원화와 에너지 수입의존도를 선정하였으며, 원자력의 도입 여부에 따른 에너지 안보 지수의 변화를 비교함으로써 에너지 안보와 원자력 도입 여부와의 관계를 정량적으로 살펴보았다. 또한 본 연구에서 개발한 에너지 안보 지수를 이용하여 주요국의 안보 지수를 산출함으로써 우리 나라의 에너지 안보의 정도를 외국과 비교하였다. 이러한 분석을 통해 그 동안 정성적으로만 논의되어 왔던 원자력 발전의 에너지 안보에 대한 기여 효과가 보다 명확하게 정량화되어 평가될 수 있었다.

• 원자력산업
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• 제38권4호
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• pp.79-80
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• 2018

원자력산업 섹터는 에너지 산업 섹터에서 가장 선진화된 기술을 도입했으다. '디지털화'에 대한 대중 인식은 일정 부분 왜곡되어 있다. 젊은 소비자들은 원자력을 구시대의 산업으로 인식한다. 소형 원자로를 비롯한 최근 기술 발전을 고려할 때 이러한 인식은 굉장히 잘못되었다. 일반 대중은 원자력산업의 디지털화에 대해 회의적이나 원자력산업 종사자의 의견은 다르다. 25~34세의 원자력산업 종사자들 중 87%는 원자력산업의 디지털화 및 자동화에 대해 '긍정적인 변화'라고 응답했다.

• 원자력산업
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• 제8권5호통권63호
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• pp.74-79
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• 1988

원전의 안전운전을 위해 인간의 신뢰도는 매우 중요하다. 다음은 런던에서 개최된 ${\ulcorner}$Human Reliability in Nuclear Power${\lrcorner}$회의의 주요사항을 영국원자력공사(UKAEA)가 발간하는 Atom지 3월호에 게재한 내용과 IAEA주최 ${\ulcorner}$맨$\cdot$머신$\cdot$인터페이스 국제회의${\lrcorner}$에서 봉판국일 일본 통산성 자원에너지청 심의관이 발표한 일본의 맨$\cdot$머신$\cdot$인터페이스 의 현황과 전망의 개요이다.

• 방사선산업학회지
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• 제17권2호
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• pp.161-172
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• 2023

Coal-fired power plants handle large quantities of coal, one of the most prominent NORM, and the coal ash produced after the coal is burned can be tens of times more radioactive than the coal. Workers in these industries may be exposed to internal exposure by inhalation of particles while handling NORM. This study evaluated the size, concentration, particle shape and density, and radioactivity concentrations of airborne suspended particles in the main processes of a coal-fired power plant. Finally, the internal radiation dose to workers from particle inhalation was evaluated. For this purpose, airborne particles were collected by size using a multi-stage particle collector to determine the size, shape, and concentration of particles. Samples of coal and coal ash were collected to measure the density and radioactivity of particles. The dose conversion factor and annual radionuclide inhalation amount were derived based on the characteristics of the particles. Finally, the internal radiation dose due to particle inhalation was evaluated. Overall, the internal radiation dose to workers in the main processes of coalfired power plants A and B ranged from 1.47×10^-5~1.12×10^-3 mSv y^-1. Due to the effect of dust generated during loading operations, the internal radiation dose of fly ash loading processes in both coal-fired power plants A and B was higher than that of other processes. In the case of workers in the coal storage yard at power plants A and B, the characteristic values such as particle size, airborne concentration, and working time were the same, but due to the difference in radioactivity concentration and density depending on the origin of the coal, the internal radiation dose by origin was different, and the highest was found when inhaling coal imported from Australia among the five origins. In addition, the main nuclide contributing the most to the internal radiation dose from the main processes in the coal-fired power plants was thorium due to differences in dose conversion factors. However, considering the external radiation dose of workers in coal-fired power plants presented in overseas research cases, the annual effective dose of workers in the main processes of power plants A and B does not exceed 1mSv y^-1, which is the dose limit for the general public notified by the Nuclear Safety Act. The results of this study can be utilized to identify the internal exposure levels of workers in domestic coal-fired power plants and will contribute to the establishment of a data base for a differential safety management system for NORM-handling industries in the future.

• Corrosion Science and Technology
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• 제10권5호
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• pp.175-179
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• 2011

The transportation and deposition of iron corrosion products are important elements that affect both the steam generator (SG) integrity and secondary system in pressurized water reactor (PWR) nuclear power plants. Most of iron corrosion products are generated on carbon steel materials due to flow accelerated corrosion (FAC). The several parameters like water chemistry, temperature, hydrodynamic, and steel composition affect FAC. It is well established that the at-temperature pH of the deaerated water system has a first order effect on the FAC rate of carbon steels through nuclear industry researches. In order to reduce transportation and deposition of iron corrosion products, increasing pH(t) tests were applied on secondary system of A, B units. Increasing pH(t) successfully reduced flow accelerated corrosion. The effect of increasing pH(t) to inhibit FAC was identified through the experiment and pH(t) evaluation in this paper.