• Title/Summary/Keyword: Plant Evaluation

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Reliability Evaluation Considering the Information and Human Factors in the Advanced Pressurized water Reactor 1400MWe under Uncertainty (신형경수로 1400에서 정보와 인적요인을 고려한 신뢰성 평가)

  • Kang Young - Sig
    • Proceedings of the Society of Korea Industrial and System Engineering Conference
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    • 2002.05a
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    • pp.25-30
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    • 2002
  • The problem of qualitative reliability system is very important issue in the digitalized nuclear power plant, because the failure of its system brings about extravagant economic loss, extensive environment destruction, and fatal damage of human. Therefore this study is to develop the reliability evaluation model through the normalized scoring model by the quantitative and qualitative factors considering the advanced safety factors In the Advanced Pressurized water Reactor 1400MWe(APR 1400) under uncertainty Especially, the qualitative factors considering the information and human factors for the systematic and rational justification have been closely analyzed. The reliability evaluation model can be simply applied in real fields in order to minimize the industrial accident and human error in the digitalized nuclear power plant.

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Evaluation of the Ductile-Brittle Transition Behavior of fracture Toughness by Material Degradation (열화에 따른 파괴인성치의 연성-취성 천이거동 평가)

  • 석창성;김형익;김상필
    • Journal of the Korean Society for Precision Engineering
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    • v.20 no.5
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    • pp.140-147
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    • 2003
  • As the huge energy transfer systems like as nuclear power plant and steam power plant are operated for a long time at a high temperature, mechanical properties are changed and ductile-brittle transition temperature is raised by degradation. So it is required to estimate degradation in order to assess the safety, remaining life and further operation parameters. The sub-sized specimen test method using surveillance specimen was developed for evaluating the integrity of metallic components. In this study, we would like to present the evaluation technique of the ductile-brittle transition temperature by the sub-sized specimen test. The four classes of the thermally aged 1Cr-1Mo-0.25V specimens were prepared using an artificially accelerated aging method. The tensile test and fracture toughness test were performed. The results of the fracture toughness tests using the sub-sized specimens were compared with the evaluation technique of the ductile-brittle transition temperature.

Development of the Event Type Analysis System (ETAS) for the Accident Evaluation in Nuclear Power Plants (원전사고 평가를 위한 원전 사건유형분석 시스템(ETAS) 개발)

  • Choi, Young Hwan;Kim, Young Mi
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.5 no.2
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    • pp.35-39
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    • 2009
  • In this study, Event Type Analysis System (ETAS) is developed for the accident evaluation in nuclear power plant. The ETAS system can be used in supporting regulator and/or operator under event situation in nuclear power plants. The ETAS system can categorize the all transient events to 3 categories such as Down-2000, Down-2173, and Slow Fluctuation. We develop the program structure for ETAS system and web-based ETAS system. The ETAS system will be used as sub module of Knowledge-Based Event Evaluation Network (K-EvENT) which is developing for the against the accident in nuclear power plants.

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The Evaluation of Ductile-Brittle Transition of Fracture Toughness by Material Degradation (재료열화에 따른 파괴인성치의 연성-취성 천이거동 평가)

  • Kim, Sang-Pil;Kim, Hyung-Ick;Seok, Chang-Sung
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.579-584
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    • 2001
  • As the huge energy transfer systems like as nuclear power plant and steam power plant are operated for a long time, mechanical properties are changed and ductile-brittle transition temperature is raised by degradation. So it is required to estimate degradation in order to assess the safety, remaining life, and further operation parameters. The sub-sized specimen test method using surveillance specimen was developed for evaluating the integrity of metallic components. In this study, we would like to present the evaluation technique of the ductile-brittle transition temperature by the sub-sired specimen test. The four classes of the thermally aged 1Cr-1Mo-0.25V specimens were prepared using an artificially accelerated aging method. The tensile test and fracture toughness test were performed. The results of the fracture toughness tests using the sub-sized specimens were compared with the evaluation technique of the ductile-brittle transition temperature.

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A Study on the Relationship between Steam Generator Fouling and the Electric Power (증기발생기 파울링과 전기출력의 상관성 고찰)

  • Cho, Nam Cheoul;Shin, Dong Man;Kim, Yong Sik
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.13 no.2
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    • pp.31-37
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    • 2017
  • The heat transfer function or thermal performance is the most important function of the steam generator component in nuclear power plants. The declining of thermal performance, fouling does not affect the electric power of the nuclear power plant within a certain fouling level, but it affects the output when goes beyond the governor valve wide open of the turbine. The VWO steam pressure can be predicted through the thermal performance evaluation of steam generators in the nuclear power plant. In consideration of the fouling characteristics of the steam generator, methods of the thermal performance evaluation and fouling cases are reviewed, and also the critical VWO value is estimated through the actual thermal performance evaluation. It is necessary to apply the VWO theory based on the thermal performance of the steam generators.

Current Status and Prospects for the Quality Evaluation of Medicinal Plants (약용식물의 품질평가 현황과 전망)

  • 김관수;류수노
    • KOREAN JOURNAL OF CROP SCIENCE
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    • v.47
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    • pp.186-199
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    • 2002
  • This is a brief review and discussion for present status and prospects of quality evaluation in medicinal plants as oriental medicine materials (OMM). Quality in medicinal plants could be defined as the combination of origin, external appearance, effectiveness and safety, and be evaluated by plant taxonomic, morphological, physiochemical and biological methods. For high-quality improvement and standardization of OMM, medicinal plants should be produced through using proper species or good variety and standard cultivation method in suitable cultivation area. Standardizing of quality means to meet with minimum qualifying criteria of OMM in the market while improving of quality to be over standard quality of medicinal piano in production. For making new high quality and standardized products, we need to keep standard field plants, standard OMM, standard plant specimen, and standard compounds. Researchers and administration have to study and propose the quality factors and their evaluating techniques and criteria, so high-quality and standardized produce of medicinal plane could be produced and distributed under the control of the relevant regulations, and would be contributed to increasing of national health.

Economic Evaluation of Power Grid Interconnection between Offshore Wind Power Plants (해상풍력발전단지 간의 전력계통 연계에 관한 경제성 분석 연구)

  • Moon, Won-Sik;Jo, Ara;Kim, Jae-Chul
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.63 no.4
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    • pp.339-344
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    • 2014
  • An offshore wind power plant (WPP) is very expensive and different from an onshore wind power system in many ways. There has been a continuous increase in the capacity of the offshore WPPs. Therefore it is essential to analyze the feasibility and reliability of the offshore wind power to optimize their redundancy. Besides, it is very important to study a planning for grid interconnection of adjacent offshore WPPs. This paper proposes a economic evaluation method to interconnect with adjacent offshore substations in offshore wind power grid. Also, we suggest the probabilistic reliability method to calculate a probabilistic power output of the wind turbine and a cost of the expected energy not supplied that is used as the reliability index of the power system.

Evaluation of New Design Concepts for Steam Generators in Sodium Cooled Liquid Metal Reactors

  • Kim, Seong-O.;Sim Yoonsub;Kim, Eui-kwang.;Myung-Hwan.Wi;Han, Dohee.
    • Nuclear Engineering and Technology
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    • v.35 no.2
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    • pp.121-132
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    • 2003
  • To reduce the construction cost and enhance the safety of sodium cooled liquid metal reactors, various kinds of new design concepts were evaluated using the KALIMER operation condition. The required equipment sizes were set for plant electricity output to be similar to that of KALIMER. The evaluations were made focusing on the plant performance and implementation practicality. Each design concept was evaluated for the concept itself and design impacts to interfacing systems. Through the evaluation of the concepts, it was found that the most favorable design concept is the integrated steam generator with forced convection using lead bismuth as the intermediate heat transfer fluid between the primary sodium tube and feed water/steam tube in the steam generator.