Relevant bibliographies by topics / Nuclear power station Dukovany

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Nuclear power station Dukovany'

Author: Grafiati
Published: 4 June 2021
Last updated: 2 February 2022

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Journal articles on the topic "Nuclear power station Dukovany"

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Hubka, Vit, Stephen W. Peterson, Jens C. Frisvad, Takashi Yaguchi, Alena Kubátová, and Miroslav Kolařík. "Aspergillus waksmanii sp. nov. and Aspergillus marvanovae sp. nov., two closely related species in section Fumigati." International Journal of Systematic and Evolutionary Microbiology 63, Pt_2 (February 1, 2013): 783–89. http://dx.doi.org/10.1099/ijs.0.047076-0.

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Two new and phylogenetically closely related species in Aspergillus section Fumigati are described and illustrated. Homothallic Aspergillus waksmanii sp. nov. was isolated from New Jersey soil (USA) and is represented by the ex-type isolate NRRL 179T ( = CCF 4266T = Thom 4138.HS2T = IBT 31900T). Aspergillus marvanovae sp. nov. was isolated from water with high boracic acid anions content in Dukovany nuclear power station (Czech Republic). The sexual stage of this species is unknown, but the MAT1-1 locus was successfully amplified suggesting that the species is probably heterothallic and teleomorphic but is represented by only the ex-type isolate CCM 8003T ( = CCF 4037T = NRRL 62486T = IBT 31279T = IFM 60873T). Both species can be distinguished from all previously described species in section Fumigati based on morphology, maximum growth temperature, sequence data from five unlinked loci and unique secondary metabolites profiles.
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Ansorge, Libor, and Jiří Dlabal. "Comparative water scarcity footprint study of two nuclear power plants." Przegląd Naukowy Inżynieria i Kształtowanie Środowiska 26, no. 4 (December 30, 2017): 489–97. http://dx.doi.org/10.22630/pniks.2017.26.4.47.

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This study compares the Life Cycle Assessment based Water Scarcity Footprint of produced energy unit in two nuclear power plants in the Czech Republic between 2005 and 2015. Primary data has been used to allocate impacts to the core processing stage. Although the real total amount of water consumption in both power plants is similar, the water scarcity footprint in Temelín nuclear power plant is of approximately 8.9 m3 H2Oeq per MWh lower than in Dukovany power plant. The cooling water has the most significant contribution to the freshwater availability impact category. Evaporation from reservoirs which are a part of water management of the individual power plants has lower, but not inconsiderable, contribution to the water consumption. In the case of Temelín nuclear power plant, the loss caused by evaporation from Hněvkovice reservoir is of approximately 6.5% of the difference between withdrawal and discharge of the power plant. In the case of Dukovany nuclear power plant, evaporation from Dalešice - Mohelno reservoir is of even around 11%.
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Kulovany, J. "Transport of Radioactive Waste in the Nuclear Power Plant at Dukovany." International Journal of Radioactive Materials Transport 5, no. 1 (January 1994): 43–45. http://dx.doi.org/10.1179/rmt.1994.5.1.43.

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Joch, Lukas, and Roman Krautschneider. "VVER-440 Steam Generator’s Two-Phase Flow Analysis." Applied Mechanics and Materials 821 (January 2016): 57–62. http://dx.doi.org/10.4028/www.scientific.net/amm.821.57.

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The subject of this report is creation of three-dimensional thermal hydraulic model of horizontal steam generator for Dukovany nuclear power plant. A procedure is presented for simulation and analysis of secondary side of PGV-440 steam generator for nominal and increased reactor power. A two-fluid approach is applied for modeling physical processes inside the steam generator. Physical models were implemented in ANSYS Fluent CFD environment using User Defined Functions (UDFs). Results from this thermal hydraulic numerical model can be used for various other subsequent nuclear power plant operations and safety analysis.
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Kozlová, Kateřina, Karla Barčová, and Jan Kubíček. "Analysis of Data Collected at Control Room Full Scope Simulator at Dukovany Nuclear Power Plant." TRANSACTIONS of the VŠB – Technical University of Ostrava, Safety Engineering Series 12, no. 2 (September 1, 2017): 11–22. http://dx.doi.org/10.1515/tvsbses-2017-0010.

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Abstract This article describes a computer program that will be used by experts to analyze human factor reliability when analyzing data obtained during the training of operators on a nuclear power plant's control room simulator. The program was applied to data collected during the training of a scenario called Rupture of the Hot Loop of the Primary Circuit (250 t/h). Based on the comparison of charts, temporal passage through the scenario, or by personal participation in the training, analysts evaluate the successful passing of the practice scenario and propose final recommendations. The article also describes the criteria for successfully passing the practiced scenario and its final evaluation.
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Kralik, Miloslav, Vladimír Kulich, and Jiri Studeny. "Dosimetry at the Interim Spent Fuel Storage Facility of the Czech Nuclear Power Plant Dukovany." Journal of Nuclear Science and Technology 37, sup1 (March 2000): 762–66. http://dx.doi.org/10.1080/00223131.2000.10874992.

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EGASHIRA, Tadahiko. "Decommissioning of nuclear power station." Doboku Gakkai Ronbunshu, no. 355 (1985): 174–79. http://dx.doi.org/10.2208/jscej.1985.355_174.

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Juraku, Kohta. "Safety of Nuclear Power Station." Journal of the Atomic Energy Society of Japan 61, no. 3 (2019): 233–36. http://dx.doi.org/10.3327/jaesjb.61.3_233.

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Vedernikov, Mikhail. "Nuclear Dilemma in Czech-Russian Relations." Scientific and Analytical Herald of IE RAS, no. 1 (February 28, 2021): 81–88. http://dx.doi.org/10.15211/vestnikieran120218188.

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The article discusses the issue of construction of two additional power units of the Dukovany NPP which gained widespread attention in the second half of 2020. The author's attention is focused on the discussion of Czech politicians and entrepreneurs regarding the participation of the Russian company Rosatom in this project. The opposition to Prime Minister A. Babiš takes an irreconcilable position, demanding to exclude it under the pretext of a geopolitical threat from the Russian Federation. As shown in the work, the head of government has to balance between the interests of big business, whose representatives demand to speed up the project development process, and anti-Russian politicians, whose support, as shown by recent polls, is increasing. It is likely that in the fall of 2021, after the next parliament elections, they will form a new government. In such circumstances, one should not count on an improvement in Czech-Russian relations.
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Chan, Yea-Kuang, and Yu-Ching Tsai. "Power uprate operation at Chinshan Nuclear Power Station." Nuclear Engineering and Design 343 (March 2019): 96–102. http://dx.doi.org/10.1016/j.nucengdes.2019.01.001.

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Dissertations / Theses on the topic "Nuclear power station Dukovany"

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Kissler, Martin. "Modernizace Jaderné elektrárny Dukovany." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2015. http://www.nusl.cz/ntk/nusl-231807.

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Thesis focuses on a detailed technical description of all important parts of secondary circuit in Dukovany power plant and its connection to other systems of power plant. In thesis are analyzed significant adjustments which have been made during the entire operation of power plant including in particular the actions associated with project called Utilization of project reserves of units EDU. In the main part of the thesis were carried out calculations of the power plant's power for states before and after the modernization and there is also analyzed the impact of individual changes on the whole power plant. These changes are with the entire secondary circuit drawn in the T-s diagram.
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Šula, Vladimír. "Zajištění datové komunikace digitálních ochran a terminálů do monitorovacího systému jaderné elektrárny Dukovany." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2015. http://www.nusl.cz/ntk/nusl-221205.

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This thesis describes the provision of the data communication of the new protection relays via 6 kV switch gears to the electro monitoring system at the Dukovany Nuclear Power Station. These protection relays will replace the current analog protection. The replacement process will start in 2015 and will finish in 2018. Given the overall complexity of the project, this thesis deals only with the following 6 kV switch gears 9BB and 9BD. The thesis is divided into a theoretical and a practical part. The theoretical part concerns the actual consumption and output of the Dukovany Nuclear Power Station. The following chapters describe the electro monitoring system and GRAF and LOGA software programs that are closely connected with it and that were used in the practical part. The last chapter of the theoretical part deals with the actual replacement of the protection relays of the 6 kV switch gears. Also, it describes a new optical network, which will be set up at the Dukovany Nuclear Power Station as a part of the process of replacement. The segment of the practical part concerns laboratory verification of the data communication of the new protection relays. Next, it describes actions that had to be taken in order to ensure and verify correct functionality of the data communication. This part is followed up by a closely related practical activity, which describes examination and verification of the protection functions of each of the 9BB and 9BD switch gears protection relays.
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Sobotková, Monika. "Facelift EDU." Master's thesis, Vysoké učení technické v Brně. Fakulta stavební, 2020. http://www.nusl.cz/ntk/nusl-414287.

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The master thesis deals with the facelift of the forecourt of the Dukovany Nuclear Power Station . This space consists of supporting functions for the main working such as administrative, metrology, stocks, cloakrooms and services. There is also the station for the buses, which carry employees to and from work, the regular bus station and parking lots. The forecourt of the power station is now inconvenient from a functional point of view, because the capacity of the existing buildings and parking lots is insufficient; and also from aesthetic point of view, because the buildings from 70’s don’t look good anymore, the parking consists of the large asphalt areas and there is no representative anteroom in front of the main entry, which should be there in view of the significance of the power station. In the study I deal with these problems by the complex reconstruction of the area, I replace the huge asphalt parking lots with the parking houses, create the administrative zone with the public place in front of the main entry to the plant, extend the capacities for the particular functions and add the new required functions (kindergaten, other services). The result of this conversion is the area with the particular functional zones with the representative forecourt in front of the main entry and with the enough space for each of the functions. This work follows up the last semester urbanist-architectonic study. The diploma thesis focus on the improvements of the weaker parts of the prime study and on the elaboration of the architectural study of the adminstrative zone with services.
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Rygl, Filip. "Výroba utahováku matice oběžného kola čerpadla." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2020. http://www.nusl.cz/ntk/nusl-417124.

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This thesis solves the problem of design and production of a special mounting device for the impeller nut of the main circulation pump GCN-317. The proposed device is intended to solve the problems associated with the mounting and dismounting of this nut. The work provides basic information about the Dukovany Nuclear Power Plant and VVER-440 systems in general, including their brief history. It also introduces the operational and legislative environment of the primary circuit of the nuclear power plant. It deals with the task and technical description of the main circulation pump and its overhaul. The following sections present the basic principles of construction of the device and an overview of its components with a description of their purpose and method of production. The last part of the thesis describes the function of the device and its verification and reports on its deployment.
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Tomoryová, Bianka. "Facelift EDU." Master's thesis, Vysoké učení technické v Brně. Fakulta stavební, 2020. http://www.nusl.cz/ntk/nusl-414291.

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The subject of the diploma thesis is an architectural study of the forecourt of the Dukovany Nuclear Power Station. The project is based on a pre-diploma project which aimed to develop an urban concept. At the moment the buildings in the area are in an unsuitable condition from a construction - technical and architectural perspective. The urban-architectural study was intended to create a new concept for the forecourt and simultaneously enable its efficient operation in case of the completion of a new nuclear unit. The concept of the solution is based on the removal of outdated buildings and their replacement with new buildings which will meet the current requirements of the Dukovany Nuclear Power Station. From the current layout the main roads, the gatehouse, the information center and the greenery will be preserved. After removing the selected buildings, the renovation area will be divided into the main axes on which the main road network will be designed. The unsuitable connection to public road infrastructure will be solved by minimizing the entrances to the area to two entrances and by moving the suburban bus station from the main road. After connecting the whole area by roads, the area will be divided into functional areas. In front of the gatehouse there will be a square surrounded by public services, an administrative building and by the preserved information center building. From this space, the main representative space of the entire complex will be created. Warehouses and workshops will be located behind the square. Transport areas will be located at the rear of the complex. Thanks to this location, there will be a good connection with the current factory and also with the planned completion of the new nuclear unit on the west of the area. There will also be educational and sport facilities in the complex. The kindergarten will be oriented towards the preserved greenery.
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Rokotianskaia, Kseniia. "Facelift EDU." Master's thesis, Vysoké učení technické v Brně. Fakulta stavební, 2020. http://www.nusl.cz/ntk/nusl-414282.

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The subject of the diploma thesis is the elaboration of an architectural study of the reconstruction of the pre-plant zone of the Facelift of the Dukovany power plant. The construction site is an area that belongs to the village of Dukovany and borders the village of Rouchovany. As a whole, this area is in poor technical and architectural condition. However, its location gives potential for new uses. The solved area belongs to the ČEZ nuclear power plant.
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Zhakupbekova, Rakhil. "Facelift EDU." Master's thesis, Vysoké učení technické v Brně. Fakulta stavební, 2020. http://www.nusl.cz/ntk/nusl-414302.

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The subject of the diploma thesis is the elaboration of an architectural study of the reconstruction of the pre-plant zone of the Facelift of the Dukovany power plant. The construction site is an area that belongs to the village of Dukovany and borders the village of Rouchovany. As a whole, this area is in poor technical and architectural condition. However, its location gives potential for new uses. The solved area belongs to the ČEZ nuclear power plant.
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Růžičková, Tereza. "Facelift EDU." Master's thesis, Vysoké učení technické v Brně. Fakulta stavební, 2020. http://www.nusl.cz/ntk/nusl-414284.

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The theme of the diploma thesis is the solution of the pre-plant zone of the Dukovany nuclear power station. Creating a vision of how this space could develop further in the next 50 years and how it could work in a transitional phase during the construction of a new nuclear power plant unit. The subject of the thesis is the elaboration of an architectural study, which is based on an urban study. Urban study was processed within the framework of the pre-diploma thesis and solved mainly the overall problems of this area, the new transport connection, and the functional division of the whole area. The area was divided into three functional units, namely the transport zone, the administrative zone and the sports and education zone. At present, there are a lot of small structurally and functionally unsuitable buildings in this area. The diploma thesis deals with the design of new buildings with a clear functional use in the administrative zone, in the area in front of the main gatehouse. A new representative square was created, and three buildings are designed around it. The dominant feature of the whole area was a high-rise office building near the gatehouse. In front of the office building, towards the main road, the service building I was designed, which contains business and healthcare services. On the other side of the square was located the service building II, where there are technical services, such as workshops, warehouses and metrology. The last building solved within the diploma thesis is the building of sports and locker rooms of suppliers, which is designed behind the square near the greenery. New building copies mass of the only preserved building in this area, namely the building of the information centre. The designed building has a fitness centre and locker rooms of external workers of the power plant.
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Žák, Jiří. "Studie blackoutu s ohledem na jadernou elektrárnu Dukovany." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2013. http://www.nusl.cz/ntk/nusl-220179.

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The entire diploma thesis analyses causes, consequences and repercussions of an electricity grid network blackout and its impact to the respective consumers. Remarkable blackouts recorded since 1965 are briefly described and basic available information is considered. The grid standard fixing measures and electricity delivery priorities are characterized. The thesis also pays attention to entire Czech Republic grid availability and its blackout endurance as well as to its robustness within last several years. Indirect Fukushima event influence to the Czech Republic electricity system is mentioned. The main part of the thesis comprises of four big European grid blackouts causes and consequences, their comparison to each other and to the Dukovany nuclear power plant grid blackout drill scenario. The preventive and standard corrective measures against blackouts are pointed out.
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Ludvík, Lubomír. "Náhřev a spouštění jaderného bloku Elektrárny Dukovany po odstávce." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2016. http://www.nusl.cz/ntk/nusl-242192.

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This thesis deals with the analysis of warming and starting up the nuclear unit of Dukovany NPP after the outage. First part explains the various operating modes of nuclear power plants, specifically operating modes of Dukovany NPP. The following part contains the analysis of heat sources in the primary circuit and also the individual production and consumption of steam by the NPP. The next part deals with division into several points of the warming of the Dukovany NPP. The analysis of warming nuclear unit after a outage is made on the basis of the industry based data, measured in December 2015. The result of the analysis is determination the amount of steam passing from a another nuclear unit, which is following by the own proposal of the external steam source.
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Books on the topic "Nuclear power station Dukovany"

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Zanobetti, D. Power station simulators. Amsterdam: Elsevier, 1989.

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Bedford, Henry F. Seabrook Station: Citizen politics and nuclear power. Amherst: University of Massachusetts Press, 1990.

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Great Britain. Ministry of Agriculture, Fisheries and Food. Eastern Region. Accident emergency plan for Bradwell nuclear power station. Cambridge: MAFF, 1990.

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Massachusetts. Dept. of Public Health. Environmental monitoring activities around the Pilgrim Nuclear Power Station. Boston, Mass: Commonwealth of Massachusetts, Executive Office of Human Services, Dept. of Public Health, 1986.

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Ontario. Legislative Assembly. Select Committee on Energy. Report on Darlington Nuclear Generating Station. Toronto: Queen's Printer, 1985.

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Allen, Richard Parsons. Shippingport station aging evaluation. Washington, DC: Division of Engineering, Office of Nuclear Regulartory Research, U.S. Nuclear Regulatory Commission, 1990.

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Parker, Victoria. Chernobyl 1986: An explosion at a nuclear power station. Oxford: Raintree, 2007.

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Great Britain. Ministry of Agriculture, Fisheries and Food. South Western Region. Accident emergency plan for Oldbury Nuclear Power Station 1990. Gloucester: Ministry of Agriculture, Fisheries and Food, Gloucester Divisional Office, 1990.

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Great Britain. Ministry of Agriculture, Fisheries and Food. Eastern region. Accident emergency plan for Sizewell nuclear power station 1990. Cambridge: Ministry of Agriculture, Fisheries and Food, Eastern Region, 1990.

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Chernobyl 1986: An explosion at a nuclear power station. Chicago, Ill: Raintree, 2006.

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Book chapters on the topic "Nuclear power station Dukovany"

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Dienstbier, Jiri, Stanislav Hustak, and Adolf Rydl. "Level 2 PSA for the VVER 440/213 Dukovany Nuclear Power Plant." In Probabilistic Safety Assessment and Management, 296–301. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_48.

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Ishikawa, Michio. "Three Mile Island Nuclear Power Station Accident." In A Study of the Fukushima Daiichi Nuclear Accident Process, 3–33. Tokyo: Springer Japan, 2015. http://dx.doi.org/10.1007/978-4-431-55543-8_1.

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Jervis, M. W. "Models and Simulation in Nuclear Power Station Design and Operation." In Advances in Nuclear Science and Technology, 77–115. Boston, MA: Springer US, 1986. http://dx.doi.org/10.1007/978-1-4613-2183-5_2.

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Holt, G., and D. L. Brown. "Large Transport and Disposal Packages for Nuclear Power Station Decommissioning Waste." In Transportation for the Nuclear Industry, 157–68. New York, NY: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4757-0046-6_16.

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Bertini, R., C. D’Anna, A. Ceccolini, G. Cuttica, and A. Linari. "Transport of Spent Fuel from Garigliano Power Station to an AFR Repository." In Transportation for the Nuclear Industry, 321–33. New York, NY: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4757-0046-6_32.

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Tanaka, Satoru, and Shinichiro Kado. "Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station." In Reflections on the Fukushima Daiichi Nuclear Accident, 51–83. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-12090-4_3.

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Abe, Hiroyasu. "Ground Motion Prediction for Regional Seismic Risk Analysis Including Nuclear Power Station." In Resilience: A New Paradigm of Nuclear Safety, 221–27. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-58768-4_17.

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Tao, Chen, Zhang Jinlong, Liu Shan, and Yu Benhai. "Fuzzy Real Option Analysis for IT Investment in Nuclear Power Station." In Computational Science – ICCS 2007, 953–59. Berlin, Heidelberg: Springer Berlin Heidelberg, 2007. http://dx.doi.org/10.1007/978-3-540-72588-6_152.

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Ren, Shuai, and Hong Qian. "The Early Warning System of Nuclear Power Station Oriented to Human Reliability." In Communications in Computer and Information Science, 206–16. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-6364-0_21.

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Chen, Ying-min, Hai-yan Deng, and Fei Wang. "The Influence of Nitric Acid on Iron Ion on the Primary Loop of Nuclear Power Station." In Challenges of Power Engineering and Environment, 1037–39. Berlin, Heidelberg: Springer Berlin Heidelberg, 2007. http://dx.doi.org/10.1007/978-3-540-76694-0_191.

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Conference papers on the topic "Nuclear power station Dukovany"

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Kotouč, Miroslav. "Analyses of Severe Accident Sequences in the Spent Fuel Pool of the VVER-1000 Type of Reactor With MELCOR 1.8.6." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30406.

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Since the Fukushima nuclear disaster in 2011, much attention has been paid to investigation of severe accidents (SA) progression in spent fuel pools (SFP) of various types of nuclear power plants (NPP). In Czech Republic, 4 VVER-440 and 2 VVER-1000 types of reactors (at the Dukovany and Temelin NPPs, respectively) are currently under operation. In order to enhance their safety, especially with respect to station black-out (SBO) events, numerical analyses have been carried out evaluating the risks associated with accidents occurring also in the SFP. The present paper deals with analyses of 2 postulated scenarios (loss of cooling and loss of coolant) and is mainly focused on the input deck preparation for the integral, lumped parameter (LP) code for SA analyses — MELCOR 1.8.6. Emphasis is put on description of correct implementation of the complex geometry of the SFP, consisting of 3 distinct pools separated by concrete walls (lined with steel plates) in which fuel assemblies (FA) are stored in an absorber grid (rack). In the description of the prepared numerical model, light is shed on the encountered modeling issues, and corresponding hints and solutions are proposed in order to provide guidance for preparing adequate models for various types of SFP designs. Finally, some of the most characteristic results are presented for both postulated scenarios.
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Brumovsky, Milan. "Lifetime Management of WWER Reactor Pressure Vessels." In ASME/JSME 2004 Pressure Vessels and Piping Conference. ASMEDC, 2004. http://dx.doi.org/10.1115/pvp2004-2972.

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Reactor pressure vessels are the most important components of nuclear power plants from safety and economic point of view. Thus, special interest is given to their lifetime management that requires a precious and periodical evaluation of their conditions. In Czech Republic, special program has been prepared for reactor pressure vessels in both nuclear power stations — Dukovany NPP with 4 units of WWER-440 MW and Temelin with 2 units of WWER-1000 MW reactors. This program is based on the following activities: • detailed calculations of real and potential regimes, especially of pressurized thermal shock events, • determination of vessel properties on the basis of testing surveillance specimens from standard, modified and supplementary programs, • calculations of neutron fluences on vessel wall, • measurements of neutron fluences on surveillance specimens and in vessel cavity, • evaluation of all results, evaluation of fluence and material property trends, • recommendations for future reactor pressure vessel operation (potential mitigation measures). The paper describes in detail all these activities and gives examples of their results and final evaluations. Lifetime assessment is based on a “Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs (VERLIFE)” using “Master Curve” approach for vessel integrity evaluation [1].
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Pistora, Vladislav, and Pavel Kral. "PTS Evaluation for Czech Nuclear Power Plants of WWER Type." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77405.

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There are two NPPs operated in the Czech Republic: NPP Dukovany of WWER 440/213 type and NPP Temelin of WWER 1000/320 type. Four units of NPP Dukovany have started their operation during 1985 – 1987, two units of NPP Temelin have been put into operation during 2002 – 2003. Pressurised-thermal shock evaluation, i.e. assessment of resistance of reactor pressure vessel (RPV) against fast fracture, was for both NPPs performed during the plant operation. For NPP Dukovany the PTS evaluation started in 1996 and the project was completed in 2004. For NPP Temelin the PTS project was conducted during 2001 – 2004. At the beginning of the project for NPP Dukovany the PTS evaluation was performed according to the IAEA “Guidelines on PTS Analysis for WWER NPP” [1]. At later phases of this project and for the whole project of NPP Temelin, the appropriate PTS evaluations were performed according to the IAEA PTS Guidelines, Revision 1 [2] and the “Unified Procedure VERLIFE” [3]. The PTS analyses consisted of two main parts: 1) Thermal hydraulic (TH) analyses: The system TH analyses were performed mainly with using the RELAP5 computer code. Reactor coolant system, secondary circuit, and emergency core cooling system were modelled in a very detailed way according to the actual NPP configuration, signals specific to the NPP were built into the models and operator actions were taken into account for some PTS transients. For relevant cases, the behaviour of media in such components as hermetic confinement (NPP Dukovany), containment (NPP Temelin), sumps and ECCS coolers, was investigated by MELCOR or RELAP5 code with primary objective — to determine the exact temperature of water from safety injection system. The detailed TH mixing analyses were performed for all non-symmetric cases using CATHARE (with 2-D model of reactor downcomer) or REMIX/NEWMIX codes. 2) Structural Analyses: All computations were focused on circumferential welds in the beltline zone. The overall approach to the analyses (for the final stages of the projects) was as follows: Temperature and stress fields were computed by finite element method (FEM) on RPV model with crack included in the mesh. SYSTUS FEM code was used for this purpose, with elastic-plastic modelling of material properties. After performing the stress analysis, the energy release rate G was calculated using the postprocessor of SYSTUS code. Finally, the stress intensity factors KI were computed based on values of G. The defects were finally postulated as semielliptical underclad cracks, both axial and circumferential, with aspect ratios a/c = 0.3 and 0.7 and with the depth 1/10 of the wall thickness. Maximum allowable critical temperature of brittleness Tka was determined by comparison of KI and [KIC]3 (the allowable value of stress intensity factor) curves. Some examples of results are presented in the paper.
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Hust’ák, Stanislav. "Experience Gained From the Living PSA Project for Dukovany NPP." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30391.

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PSA specialists in ÚJV Řež, a. s. maintain a Living Probabilistic Safety Assessment (Living PSA) program for Dukovany Nuclear Power Plant (NPP), a four-unit VVER-440 plant type, which is operated in the Czech Republic. This project has been established as a broad framework for all plant activities related to risk assessment and as a support for risk-informed decision making carried out at this plant. In addition to recommendations for design and operation measures in order to increase the plant safety, it provides a basis and platform for all PSA applications at Dukovany NPP. The Living PSA model for Dukovany NPP is an integrated model representing the complete scope of Level 1 and Level 2 PSA for all plant operational modes. It produces the unit specific outputs for any Dukovany NPP unit. The RiskSpectrum® PSA software has been used for development and quantification of the PSA model. It is continuously updated and extensively used for various PSA applications at Dukovany NPP (e.g. risk monitoring, evaluation of plant Technical Specification changes, support for procedure development and training process, event analysis, etc.). The paper focuses on the important features of the Living PSA project for Dukovany NPP. It also discusses the broad experience gained during model development and update as well as possible future enhancements.
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Pliska, Jiri, Zdenek Machat, Libor Veznik, and Jiri Smisek. "Thermal Performance Monitoring and Optimization in Dukovany NPP." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30735.

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Competition in the electricity market forces producers to achieve — in compliance with safety — efficiency of production as high as possible. This efficiency and heat rate is an important indicator of both the condition of the power plant equipment and the quality of power plant operation. To cope with these challenges, powerful methods are process data reconciliation, statistical data processing of large data sets and process simulation. These functions and methods can be used to obtain useful information about process quality and equipment and sensor health. The paper discusses practical experience from six years of using a thermal performance monitoring and optimization system in the Dukovany nuclear power plant. The system is integrated into the overall nuclear power plant process information system and data warehouse. The system provides information in near real time. The major benefit of the system lies in a deep view into equipment behaviour and process which ensures timely detection and identification of functionality degradation of process and equipment or sensor faults. The system also helps to find and use margins of equipment operation and the overall thermal cycle. Selected practical examples are used to demonstrate specific benefits of the system for operation and maintenance of the Dukovany nuclear power plant. There are examples of equipment fault detection and sensor degradation detection. The optimization function is explained with an example of cooling circuit optimization aimed to increase the delivery of electrical power into the grid. A detailed description of behaviour of the main components can be used for their performance evaluation and their repair planning. The benefit of more accurate determination of parameter values is reflected in more accurate determination of reactor thermal output. The conclusion of the paper provides an overall evaluation of system benefits for operation and maintenance of a nuclear power plant.
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Belatka, M., B. Batora, and A. Matousek. "Development of 5-year refuelling cycle at Dukovany Nuclear Power Plant, Czech Republic." In 2008 International Conference Modern Technique and Technologies - (MTT 2008). IEEE, 2008. http://dx.doi.org/10.1109/spcmtt.2008.4897513.

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Palaric, Jean-Michel, Philippe Rebreyend, Philippe Mouly, Claude Esmenjaud, and Frantisˇek Dalik. "Modernization of the Safety I&C at the Dukovany VVER 440/213 Nuclear Power Plant." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75706.

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The modernization of the Dukovany nuclear power plant (four VVER 440 MWe reactor units owned by CˇEZ, the Czech national utility) is presented with a special focus on the digital safety instrumentation and control (I&C) system. The first Unit has been successfully modernized in compliance with the initial schedule. The following matters are further discussed in this paper: • Goal, scope and industrial organization of this modernization, • Main design criteria and I&C architecture, • Digital technologies in use, • Design and Licensing processes, • On-site installation strategy and main milestones, • Progress of work.
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Liu, Yuanyuan. "Nuclear Power Station Development History." In 7th International Conference on Education, Management, Information and Mechanical Engineering (EMIM 2017). Paris, France: Atlantis Press, 2017. http://dx.doi.org/10.2991/emim-17.2017.136.

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McCracken, Steven L., Marek Palán, Pavel Mlynář, and Nicholas Mohr. "Full Structural Weld Overlay on a Super Emergency Feedwater Nozzle at the Dukovany Nuclear Power Plant." In ASME 2019 Pressure Vessels & Piping Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/pvp2019-93664.

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Abstract A weld overlay (WOL) following the general guidelines of ASME Code Case N-740-2 was successfully installed in March of 2018 on a dissimilar metal weld joining the super emergency feedwater1 piping to steam generator (SG) at the Dukovany nuclear power plant (NPP) in the Czech Republic. The repair was necessary due to stress corrosion cracking detected in the super emergency feedwater nozzle to safe-end dissimilar metal weld. This was the first WOL installed in the Czech Republic and represents a significant step towards further acceptance of this proven repair technology in Europe. The WOL repair approach was accepted by the Czech regulator, and two different inspection agencies, following successful mockup demonstrations, welding procedure qualification, nondestructive examination demonstrations and weld residual stress analyses. This paper describes the preparatory work as well as field deployment of WOLs in the Czech Republic.
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Asai, Yoshihisa, Toshimitsu Takagi, and Tatsuya Azuma. "Major Component Replacement Experience in IKATA Power Station." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22618.

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Unit 1 & 2 in IKATA power station, both are two-loop PWRs, have experienced major component replacement. The components are two steam generators (SG) and a reactor pressure vessel closure head (VH) for each plant and were replaced with improved ones. This paper explains the reasons for the replacement and major improvements in the components.
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Reports on the topic "Nuclear power station Dukovany"

1

Pugila, W. J. Analysis of core damage frequency: Nuclear power plant Dukovany, VVER/440 V-213 Unit 1, internal events. Volume 1: Main report. Office of Scientific and Technical Information (OSTI), December 1994. http://dx.doi.org/10.2172/74108.

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Kaminski, M. D., L. Nunez, and A. Purohit. Decontamination of control rod housing from Palisades Nuclear Power Station. Office of Scientific and Technical Information (OSTI), May 1999. http://dx.doi.org/10.2172/12083.

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Noshkin, V. E., K. M. Wong, R. J. Eagle, J. W. Dawson, J. L. Brunk, and T. A. Jokela. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station. Office of Scientific and Technical Information (OSTI), March 1985. http://dx.doi.org/10.2172/5743313.

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Vojtech, R. J. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area. Office of Scientific and Technical Information (OSTI), March 1994. http://dx.doi.org/10.2172/10152977.

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Noshkin, V. E., K. M. Wong, R. J. Eagle, J. L. Brunk, and T. A. Jokela. Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station, 1985. Office of Scientific and Technical Information (OSTI), February 1986. http://dx.doi.org/10.2172/5683150.

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Robison, W. L., Kai M. Wong, and H. E. Jones. Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station. Office of Scientific and Technical Information (OSTI), November 1990. http://dx.doi.org/10.2172/6273385.

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SULLIVAN, T. ASSESSMENT OF RADIONUCLIDE RELEASE FROM CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION. Office of Scientific and Technical Information (OSTI), March 2004. http://dx.doi.org/10.2172/15016581.

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Wesley, D. A., D. K. Nakaki, H. Hadidi-Tamjed, and T. R. Kipp. Pressure-dependent fragilities for piping components: Pilot study on Davis-Besse Nuclear Power Station. Office of Scientific and Technical Information (OSTI), October 1990. http://dx.doi.org/10.2172/6387566.

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Bonino, A., L. Pizarro, Z. Higa, S. A. Dupree, and J. L. Schoeneman. Results of the first year of operation at Embalse Nuclear Power Station in Argentina. Office of Scientific and Technical Information (OSTI), July 1996. http://dx.doi.org/10.2172/270679.

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GREENE, G. A., and J. G. GUPPY. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA. Office of Scientific and Technical Information (OSTI), August 1998. http://dx.doi.org/10.2172/760987.

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