• Title/Summary/Keyword: Energy plant

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The trend of Energy ICT in automated agriculture and EMS system for cooling water application in power plant (시설농업에서 에너지 ICT 와 발전소 온배수 활용을 위한 에너지관리시스템)

  • Hwang, Woo-jeong;Kim, Kwang-kyu
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2015.10a
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    • pp.623-625
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    • 2015
  • Recently, the cooling water of power plant was included in RPS(Renewable Portpolio Standard) as water heat energy. Thus the trend of cooling water application is growing bigger for agriculture and fishing industry. Especially as energy consumption cost in agriculture and fishing industry is a vital element, the interests for energy efficiency is growing bigger. The advanced agriculture country like Netherlands is distributing diagnosis software to the farmers based on ICT diagnostic system for the efficient energy consumption and energy demand amounts depend on crops of cultivation in automated horticulture. Hereafter, in the preparation of the expansion of the automated agriculture domestically by the cooling water of power plant, we would like to propose the energy application case(Greenery) in the advanced countries abroad in agriculture and EMS system about the application of the cooling water in power plant.

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Comparative Transcriptome Analysis of Sucrose Biosynthesis-Associated Gene Expression Using RNA-Seq at Various Growth Periods in Sugar Beet (Beta vulgaris L.)

  • Baul Yang;Ye-Jin Lee;Dong-Gun Kim;Sang Hoon Kim;Woon Ji Kim;Jae Hoon Kim;So Hyeon Baek;Joon-Woo Ahn;Chang-Hyu Bae;Jaihyunk Ryu
    • Proceedings of the Plant Resources Society of Korea Conference
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    • 2023.04a
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    • pp.63-63
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    • 2023
  • Sugar beet (Beta vulgaris L.) is one of the most important sugar crops and provides up to 30% of the world's sugar production. In this study, we mainly performed RNA-sequencing to obtain identify putative genes involved in biosynthesis pathway of sucrose in sugar beet and comparative transcriptomic analyses in the four developmental stages (50, 90, 160 and 330 days after seedling). As a result of the sugar content analysis, it was increased significantly from 50 to 160 days after seedling (DAS), and then decreased at 330 DAS. On the other hand, the taproot weight, length, and width were increased during all the growth periods. Out of 21,451 genes with expressed value, 21,402 (99.77%) genes had functional descriptions. Among the three comparisons, S1 (50 DAS) vs. S2 (90 DAS), S1 vs. S3 (160 DAS), and S1 vs. S4 (330 DAS), expression profiling of the transcripts was identified 4,991 with differentially expressed genes (DEGs). By comparing the top 20 enriched gene ontology (GO) terms as three comparisons, the top GO terms were commonly confirmed with external encapsulating structure, cell wall, and extracellular regions. In addition, the 38 enriched candidate genes related to sucrose biosynthetic pathway were screened from the entire DEG pool, and the candidate genes might be providing a basic data for further sugar metabolism studies in development of sugar beet taproot.

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Production of SCC Flaws and Evaluation Leak Behavior of Steam Generator Tubes (누설 및 파열실험용 SCC 결함 전열관 제작 및 누설거동 평가)

  • Hwang, Seong-Sik;Jung, Man-Kyo;Park, Jang-Yul;Kim, Hong-Pyo
    • Corrosion Science and Technology
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    • v.8 no.5
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    • pp.188-192
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    • 2009
  • A forced outage due to a steam generator tube leak in a Korean nuclear power plant was reported.1) Primary water stress corrosion cracking has occurred in many tubes in the plant, and they were repaired using sleeves or plugs. In order to develop proper repair criteria, it is necessary to understand the leak behavior of the tubes containing stress corrosion cracks. Stress corrosion cracks were developed in 0.1 M sodium tetrathionate solution at room temperature. Steam generator(SG) tubes with short cracks were successfully fabricated with a restricted solution contact method. The leak rates of the degraded tubes were measured at room temperature. Some tubes with 100 % through wall cracks showed an increase of leak rate with time at a constant pressure.

OTEC System using the Condenser Effluent from Nuclear Power Plant a feasibility study (원자력 발전소의 온배수를 이용한 해양온도차 발전의 타당성 검토)

  • Shin, Sangwoong;Chun, Wongee
    • 한국신재생에너지학회:학술대회논문집
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    • 2010.06a
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    • pp.238.2-238.2
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    • 2010
  • Recently, environmental pollution and energy depletion problems have been issued over the world. For this reason, many renewable systems have been developing. Of these, the Ocean Thermal Energy Conservation(OTEC) is drawing attention as the upcoming alternative energy source. In this paper, the efficiency of each of OTEC which harness the effluent from nuclear power plant was analyzed by using computer calculation. The result, shows that Ul-jin Nuclear Power Plant is the best place geographically and the regenerative cycle is most outstanding performance cycle for OTEC. The difference of temperature between surface water and deep water temperature should be greater than $20^{\circ}C$ in order to increase the efficiency.

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MIDLOOP Code Analysis of a ROSA-IV/LSTF Experiment for the Loss of Residual Heat Removal System Event During Mid- loop Operation

  • Han, Kee-Soo;Lee, Cheol-Sin;Park, Chul-Jin;Kim, Hee-Cheol
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05b
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    • pp.683-690
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    • 1996
  • The MIDLOOP code has been developed for the evaluation of RES pressurization transients initiated from a loss-of-Residual Heat Removal System (RHRS) during mid-loop operation after reactor shutdown. It provides a fast running and realistic tool for studying parametrically the response of important plant parameters such as pressure, temperature, and level to various plant combinations of the primary side vent, makeup, and leakage procedures and the steam generator (SG) conditions. The code consists of ten nodes representing the primary and secondary sides of a nuclear power plant and can analyze the effect of air on the primary system pressurization and primary to secondary heat transfer. The analysis results of the MIDLOOP code are in good agreement with the ROSA-IV/LSTF experiment without opening in the RCS.

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Feasibility Study on KSNP Adaption of French Digital Protection System

  • Koo, Jun-Mo;Lee, Young-Ryul;Jung, Ho-Chang;Chang, Ik-Ho;Han, Jai-Bok
    • Nuclear Engineering and Technology
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    • v.28 no.4
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    • pp.359-365
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    • 1996
  • Upgrade of nuclear power plant I&C systems by using digital technology has been implemented to overcome the obsolescence of existing equipment and improve plant availability in many advanced countries. For upgrade of the Plant Protection System(PPS) based on conventional analog technology in the UCN 3&4 and YGN 5&6, French modernized Digital Integrated Protection System(DIPS) with proven technology is reviewed and evaluated for the adaptability into PPS. This paper contains the results of feasibility study for the design of digital PPS using French DIPS technology. Based on the results of evaluations, the system architecture of digital PPS is designed and described.

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Control of Booster Output Voltage in Fuel Cell Power Plant (연료전지발전용 부스터의 출력전압제어 연구)

  • Han, Soo-Bin;Jung, Bong-Man;Shin, Dong-Ryul;Choi, Soo-Hyun
    • Proceedings of the KIEE Conference
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    • 1992.07b
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    • pp.1038-1040
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    • 1992
  • Booster is used widely as one of the step-up DC/DC power converter in power conversion process for fuel cell power plant which have the electrical characteristic of the high current density and low cell voltage. In view of control system, booster can be unstable when it is operated in broad operation range because the transfer function of booster has zero in right half plane of s-domain. So for reliable operation, controller must make the system stable in whole working range. In this paper, the two control method such as digital PID control and fuzzy control is studied for booster output voltage regulation in fuel cell plant. The design procedure of PID control and fuzzy control is described. And the experiment of designed controller action is performed in various operation points for controller performance test.

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Analysis of Human Errors in Trip Cases of Korean NPPs

  • Lee, Jung-Woon;Park, Geun-Ok;Park, Jae-Chang;Sim, Bong-Shick
    • Nuclear Engineering and Technology
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    • v.28 no.6
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    • pp.563-575
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    • 1996
  • A total of 77 cases was identified to have human errors from a total of 255 trips occurred from 1978 to 1992 in Korean NPPs. The cases were analyzed to investigate how many human errors occurred on which work conditions to find out the areas of high priority for human error reduction. For the analysis of the 77 trip cases due to human errors, classifications were made for the following four categories ; plant systems, work situation, job types, and error types. Erroneous tasks critically influencing the plant trips were carefully identified and analyzed according to the classifications. Based on the results for the individual cases, the cases were counted for the classification items in each of the four categories, then also for the group of categories to investigate the relationships among the categories in aspects of human error occurrences. As results, the plant systems, work situations, and job types, and error types that are dominant in human errors related to the trips ore identified.

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Smart Grid Utilization of modern technology in agriculture (스마트 그리드 기술의 현대농업에의 활용방안)

  • Kim, Kwang-Man
    • Journal of the Korea Safety Management & Science
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    • v.14 no.4
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    • pp.211-218
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    • 2012
  • In this paper, we propose a system architecture of the AMI to be applied in the modern agricultural sector. Agricultural electricity costs in South Korea is very inexpensive compared with other industries. It is expected to increase oil prices to rise over the medium to long term so the facilities must to be installed for farmers in terms of energy savings and energy costs. The research and development of plant factory which can replace the ills of modern agriculture is very active. The technologies of smart grid and plat factory are good paradigm of next generation agricultural sector. Good use of smart grid technologies, the traditional energy consumption industries, agriculture sector can be self-sufficiency industry. In this article the AMI architecture is developed and it will be applicable for modern farmers plant factory.

A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I) (원자력발전소(原子力發電所) 가동중(稼動中) 검사(檢査)의 시험분석(試驗分析)을 위한 자동화연구(自動化硏究) (I))

  • Kim, W.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.5 no.1
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    • pp.34-47
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    • 1985
  • The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during preservice and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant ${\ast}$ General Requirement. ${\ast}$ Principle and Methods of Ultrasonic Test. ${\ast}$ Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspite of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huze system, the more notice should be concentrated as follows. Establishing rational operation plan, developing various technology, and making the newly designed system for undeveloped sector.

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