• Title, Summary, Keyword: Nuclear Power Plant

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Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

  • Choi, Won-Jun;Roh, Myung-Sub;Kim, Chang-Lak
    • Nuclear Engineering and Technology
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    • v.49 no.3
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    • pp.525-533
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    • 2017
  • A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

Seismic Response Analysis of Nuclear Power Plant Structures and Equipment due to the Pohang Earthquake (포항지진에 대한 원자력발전소 구조물 및 기기의 지진응답분석)

  • Eem, Seung-Hyun;Choi, In-Kil
    • Journal of the Earthquake Engineering Society of Korea
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    • v.22 no.3
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    • pp.113-119
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    • 2018
  • The probabilistic seismic safety assessment is one of the methodology to evaluate the seismic safety of the nuclear power plants. The site characteristics of the nuclear power plant should be reflected when evaluating the seismic safety of the nuclear power plant. The Korea seismic characteristics are strong in high frequency region and may be different from NRC Regulatory Guide 1.60, which is the design spectrum of nuclear power plants. In this study, seismic response of a nuclear power plant structure by Pohang earthquake (2017.11.15. (KST)) is investigated. The Pohang earthquake measured at the Cheongsong seismic observation station (CHS) is scaled to the peak ground acceleration (PGA) of 0.2 g and the seismic acceleration time history curve corresponding to the design spectrum is created. A nuclear power plant of the containment building and the auxiliary buildings are modeled using OPENSEES to analyze the seismic response of the Pohang earthquake. The seismic behavior of the nuclear power plant due to the Pohang earthquake is investigated. And the seismic performances of the equipment of a nuclear power plant are evaluated by the HCLPF. As a result, the seismic safety evaluation of nuclear power plants should be evaluated based on site-specific characteristics of nuclear power plants.

PWSCC and System Engineering Development of Internal Inspection and Maintenance Methodology for RCS

  • Abdallah, Khaled Atya Ahmed;Mesquita, Patricia Alves Franca de;Yusoff, Norashila;Nam, GungIhn;Jung, JaeCheon;Lee, YoungKwan
    • Journal of the Korea Society of Systems Engineering
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    • v.12 no.1
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    • pp.89-103
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    • 2016
  • Due to safety of the plant, it became very clear the importance of study occurrence reactor coolant system (RCS) issues specially the primary water stress corrosion cracking (PWSCC). The Systems Engineering (SE) approach is characterized by the application of a structured engineering methodology for the design of a complex system or component. Robotic devices have been used for internal inspection, maintenance and performing remote welding and inspection in high-radiation areas. In this paper, PWSCC overview and inlay and over lay welding methodology introduced, concept of robotic device that can be inserted into the piping via Steam Generator (SG) main way to access to primary piping of pressurized water reactor (PWR) is developed based on SE methodology. A 3D model of the inspection system was developed along with the APR1400 (Advanced Power Reactor)reactor coolant systems (RCS) and internals with virtual 3D simulation of the operation for visualization to prove the validity of the concept.

Penetration of Korean EPC Companies into International Market for Nuclear Power Plant (플랜트 EPC 기업의 해외 원자력 발전 프로젝트 진출방안)

  • Cho, Chan-Hyoung;Moon, Seung-Jae;Yoo, Hoseon
    • Plant Journal
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    • v.5 no.3
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    • pp.66-73
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    • 2009
  • This study aims to develop a strategy for South Korean companies to penetrate into the global NPP(nuclear power plant) market with their strength as the sixth biggest nuclear power generator in the world. With 20 nuclear plants in commercial operation and 6 more in construction, South Korea has the best technology in construction and operation of NPP. Despite these capabilities as demonstrated on its domestic market, Korean companies' constraint to enter and play a key role in global NPP market would be the lack of experience in overseas NPP projects, original technologies, and diplomatic effectiveness. This study analyzes the competitiveness of Korean standardized nuclear power plant, construction management skills, construction technologies, manufacturing equipment and materials and operation skills. In this research the current status of existing NPP and the forecast of building NPP according to countries was analyzed in order to work out strategies with technology, cost-effectiveness, and diplomatic consideration.

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Kt Factor Analysis of Lead-Acid Battery for Nuclear Power Plant

  • Kim, Daesik;Cha, Hanju
    • Journal of international Conference on Electrical Machines and Systems
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    • v.2 no.4
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    • pp.460-465
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    • 2013
  • Electrical equipments of nuclear power plant are divided into class 1E and non-class 1E. Electrical equipment and systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, are classified as class 1E. batteries of nuclear power plant are divided into four channels, which are physically and electrically separate and independent. The battery bank of class 1E DC power system of the nuclear power plant use lead-acid batteries in present. The lead acid battery, which has a high energy density, is the most popular form of energy storage. Kt factor of lead-acid battery is used to determine battery size and it is one of calculatiing coefficient for capacity. this paper analyzes Kt factor of lead-acid battery for the DC power system of nuclear power plant. In addition, correlation between Kt parameter and peukert's exponent of lead-acid battery for nuclear plant are discussed. The analytical results contribute to optimize of determining size Lead-acid battery bank.

Systems Engineer Program for Practical Nuclear Power Plant Engineering Education (실용적인 원전공학 교육을 위한 시스템즈 엔지니어 프로그램)

  • Chang, Choong-koo;Jung, Jae-cheon;DIA, Aminata
    • Journal of the Korea Society of Systems Engineering
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    • v.11 no.2
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    • pp.31-40
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    • 2015
  • KEPCO International Nuclear Graduate School (KINGS) is dedicated to nurturing leadership-level professionals in nuclear power plant (NPP) engineering. KINGS have designed curriculum based on two philosophies. First, we balance aspects of discipline engineering, specialty engineering, and management engineering in the framework of systems engineering. Second, KINGS have designed the curriculum so that students can learn and experience the know-what, know-how and know-why level knowledge of NPP engineering and management. The specialization programs are opened during the 2nd year for 3 trimesters and those are a process of learning through practical project courses. The objectives of the specialization programs are to help students to learn the NPP life cycle technologies in highly structured and systematic ways. The systems engineer program (SEP) is one of the specialization programs. A practical case of the SEP which was applied to the project course for the NPP electric power system design education will be elaborated in this paper.

The Cognitive and Economic Value of a Nuclear Power Plant in Korea

  • Lim, Gil-Hwan;Jung, Woo-Jin;Kim, Tae-Hwan;Lee, Sang-Yong Tom
    • Nuclear Engineering and Technology
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    • v.49 no.3
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    • pp.609-620
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    • 2017
  • We studied the value of a nuclear power plant by considering Koreans' willingness to pay (WTP) for neutralizing the various problems caused by building and operating a new plant. For this, we used a conjoint analysis and ordered logistic regression. We then compared the WTP estimates between various segment groups. The results revealed that each household was willing to pay an additional 99,677 Korean Won (KRW)/mo on average to resolve the negative impacts from a nuclear plant. Therefore, the yearly cognitive and economic value of a nuclear plant in Korea was about 19 trillion KRW. Through a segment analysis, we found that the more educated, younger, and poorer groups gave higher cognitive values than the less educated, older, and richer groups, respectively. Also, people who lived far from a plant gave higher values than people living near a plant, and people with more knowledge about or interest in nuclear energy gave higher values than people with less knowledge or interest. People who felt that nuclear energy is necessary gave higher values to nuclear energy than those who did not. Our results can be used as bases to set targets for promoting nuclear energy and pursuing a national project of building a nuclear power plant.

Analysis of Battery Performance Test for DC Power System in Nuclear Power Plant (원자력발전소 직류전원계통용 축전지 성능시험 분석)

  • Kim, Daesik;Cha, Hanju
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.63 no.2
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    • pp.61-68
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    • 2014
  • Function of battery bank stores energy for DC load in general, and DC power system of the nuclear power plant is used to supply DC loads for safety- featured instrumentation and control such as inverter, class 1E power system control and indication, and station annunciation. Class 1E DC power system must provide a power for the design basis accident conditions, and adequate capacity must be available during loss of AC power and subsequent safe shutdown of the plant. In present, batteries of Class 1E DC power system of the nuclear power plant uses lead-acid batteries. Class 1E batteries of nuclear power plants in Korea are summarized in terms of specification, such as capacity, discharge rate, bank configuration and discharge end voltage, etc. This paper summarizes standards of determining battery size for the nuclear power plant, and analyzes duty cycle for the class 1E DC power system of nuclear power plant. Then, battery cell size is calculated as 2613Ah according to the standard. In addition, this paper analyzes performance test results during past 13 years and shows performance degradation in the battery bank. Performance tests in 2001 and 2005 represent that entire battery cells do not reach the discharge-end voltage. Howeyer, the discharge-end voltage is reached in 14.7% of channel A (17 EA), 13.8% of channel B (16 EA), 5.2% of channel C (6 EA) and 16.4% of channel D (19 EA) at 2011 performance test. Based on the performance test results analysis and size calculation, battery capacity and degradation by age in Korearn nuclear power plant is discussed and would be used for new design.