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1

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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2

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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3

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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4

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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5

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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6

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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7

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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8

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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9

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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10

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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11

ITAKURA, Tetsuro. "Radiation Protection in Nuclear Power Station." Japanese Journal of Health Physics 30, no. 2 (1995): 107–9. http://dx.doi.org/10.5453/jhps.30.107.

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12

Frantál, Bohumil, Jiří Malý, Martin Ouředníček, and Jiří Nemeškal. "Distance matters. Assessing socioeconomic impacts of the Dukovany nuclear power plant in the Czech Republic: Local perceptions and statistical evidence." Moravian Geographical Reports 24, no. 1 (March 1, 2016): 2–13. http://dx.doi.org/10.1515/mgr-2016-0001.

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AbstractThe effect of geographical distance on the extent of socioeconomic impacts of the Dukovany nuclear power plant in the Czech Republic is assessed by combining two different research approaches. First, we survey how people living in municipalities in the vicinity of the power plant perceive impacts on their personal quality of life. Second, we explore the effects of the power plant on regional development by analysing long-term statistical data about the unemployment rate, the share of workers in the energy sector and overall job opportunities in the respective municipalities. The results indicate that the power plant has had significant positive impacts on surrounding communities both as perceived by residents and as evidenced by the statistical data. The level of impacts is, however, significantly influenced by the spatial and social distances of communities and individuals from the power plant. The perception of positive impacts correlates with geographical proximity to the power plant, while the hypothetical distance where positive effects on the quality of life are no longer perceived was estimated at about 15 km. Positive effects are also more likely to be reported by highly educated, young and middle-aged and economically active persons, whose work is connected to the power plant.
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13

Pope, Daniel, and Henry F. Bedford. "Seabrook Station: Citizen Politics and Nuclear Power." Journal of American History 79, no. 4 (March 1993): 1690. http://dx.doi.org/10.2307/2080358.

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14

Patwardhan, P. K., R. K. Balani, N. D. Shirke, and A. G. Bhujle. "Computer Based Instrumentation for Nuclear Power Station." IFAC Proceedings Volumes 19, no. 16 (December 1986): 125–32. http://dx.doi.org/10.1016/s1474-6670(17)59370-2.

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15

OHTERU, Shigeru, Jun KANEKO, Toshio KAWAHARA, and Mitsuo MATSUMOTO. "Operating experience of Fugen nuclear power station." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 29, no. 5 (1987): 368–84. http://dx.doi.org/10.3327/jaesj.29.368.

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16

KERSHAW, PJ, DC WEATHERSEED, and J. POLLIN. "TORNESS NUCLEAR POWER STATION: CIVIL ENGINEERING CONSTRUCTION." Proceedings of the Institution of Civil Engineers 78, no. 5 (October 1985): 1139–63. http://dx.doi.org/10.1680/iicep.1985.921.

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17

Toporkov, R. I., and V. N. Koinov. "The Beloyarsk nuclear power station turns 45." Thermal Engineering 56, no. 11 (November 2009): 977–78. http://dx.doi.org/10.1134/s0040601509110147.

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18

Skipp, B. O. "Faults near Hinkley Point Nuclear Power Station." Quarterly Journal of Engineering Geology and Hydrogeology 21, no. 2 (May 1988): 111. http://dx.doi.org/10.1144/gsl.qjeg.1988.021.02.01.

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19

Roos, E., K. Maubach, and N. Albert. "The safety of nuclear power station components." Nuclear Engineering and Design 160, no. 1-2 (February 1996): 241–55. http://dx.doi.org/10.1016/0029-5493(95)01104-8.

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20

Keng, C. W. Kenneth. "Forecasting Canadian nuclear power station construction costs." Energy Economics 7, no. 4 (October 1985): 241–58. http://dx.doi.org/10.1016/0140-9883(85)90046-5.

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21

Heising, Carolyn D., and Henry F. Bedford. "Seabrook Station: Citizen Politics and Nuclear Power." New England Quarterly 64, no. 2 (June 1991): 337. http://dx.doi.org/10.2307/366138.

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22

Wang, Yu Lan. "Safety Performance Evaluation of Nuclear Power Station Containment." Applied Mechanics and Materials 672-674 (October 2014): 418–21. http://dx.doi.org/10.4028/www.scientific.net/amm.672-674.418.

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Nuclear energy as an economical, safe and clean energy is being increasingly concerned, and nuclear power stations have also been widely built in the world. However, because of the impact from nuclear events, the safety of nuclear power station has been suspected by the public. First, the development situation of the nuclear power station in the world is described. Then the nuclear power station containment is introduced. Meanwhile, the safety performance of nuclear power station containment under external events are analyzed. Some advices on guaranteeing the security work of nuclear power station containment are given.
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23

Lipták, Ľudovít, Eva Fojcíková, Monika Krpelanová, Miroslav Chylý, and Peter Čarný. "ESTE ANNUAL IMPACTS—SYSTEM FOR ASSESSMENT OF RADIOLOGICAL IMPACTS OF OPERATIONAL DISCHARGES FROM NUCLEAR FACILITIES." Radiation Protection Dosimetry 186, no. 2-3 (December 2019): 315–20. http://dx.doi.org/10.1093/rpd/ncz225.

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Abstract Described are models and approaches of the software tool ESTE Annual Impacts, a system for analyzes of radiological impacts of operational discharges to the atmosphere and hydrosphere from nuclear facilities. As a result, evaluated are radiological impacts to the population (to representative person and collective doses) and the environment (plants and animals). Described are models applied for calculation of dispersion in the atmosphere and hydrosphere (river, dam, sea). Method of application of sea currents for dispersion calculation in marine environment is also presented. The system is used by operators of the operated and decommissioned nuclear facilities at the site Bohunice (Slovakia), by regulatory authority of the Czech Republic for facilities at the sites Dukovany and Temelín and by operator of the Bushehr Nuclear Power Plant (Iran). In addition, the system is tool for analyses of environmental impacts assessments, applied in environmental impacts assessments process for newly prepared nuclear sources in Slovakia and Czech Republic.
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24

AKIZUKI, Teruo, Koji OKAMOTO, and Tadashi NARABAYASHI. "The Research Committee of Chuetsu-Oki Earthquake Influences to Kashiwazaki-Kariwa Nuclear Power Station(Survey of Kashiwazaki-Kariwa Nuclear Power Station)(Chuetsu-Oki Earthquake Influences to Nuclear Power Station,Power and Energy System Symposium)." Transactions of the Japan Society of Mechanical Engineers Series B 75, no. 751 (2009): 445–46. http://dx.doi.org/10.1299/kikaib.75.751_445.

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25

MIYANO, Hiroshi, Toshiyuki TAKAGI, and Shinsuke SAKAI. "The Research Committee of Chuetsu-Oki Earthquake Influences to Kashiwazaki-Kariwa Nuclear Power Station : Seismic Margin on Nuclear Power Station Design(Chuetsu-Oki Earthquake Influences to Nuclear Power Station,Power and Energy System Symposium)." Transactions of the Japan Society of Mechanical Engineers Series B 75, no. 751 (2009): 450–52. http://dx.doi.org/10.1299/kikaib.75.751_450.

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26

NARIAI, Hideki. "On the Fukushima Daiichi Nuclear Power Station Accident." RADIOISOTOPES 61, no. 4 (2012): 193–207. http://dx.doi.org/10.3769/radioisotopes.61.193.

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27

Zhang, Shao Bo, Bi Xiong Luo, Xu Bin Qiao, Juan Chen, and Xiao Dong Wang. "FeedWater System Transient Analysis of Nuclear Power Station." Advanced Materials Research 347-353 (October 2011): 1557–60. http://dx.doi.org/10.4028/www.scientific.net/amr.347-353.1557.

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Nuclear power station has high safety requirements, and the safety systems related to the nuclear island must be checked by hydraulic calculation. In the conventional island, the safe shutdown of the nuclear island most closely relates to the feedwater system, which determines the quantity and quality of the feedwater supply to the steam generator. In this paper, feedwater evolution in case of steamline break will be presented by using Flowmaster hydraulic software, and the results was used as the input for the analysis of security assessment in the nuclear island.
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28

Eto, Kazutoshi. "Safety Improvement Assessment on Sendai Nuclear Power Station." Journal of the Atomic Energy Society of Japan 60, no. 2 (2018): 85–88. http://dx.doi.org/10.3327/jaesjb.60.2_85.

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29

Jones, L. "Nuclear family [Hinkley Point C power station construction]." Engineering & Technology 12, no. 3 (April 1, 2017): 58–61. http://dx.doi.org/10.1049/et.2017.0305.

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30

Reilly, Michael. "Where would you like your nuclear power station?" New Scientist 195, no. 2614 (July 2007): 17. http://dx.doi.org/10.1016/s0262-4079(07)61870-3.

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31

Kochetkov, L. A. "World’s first nuclear power station: Legacy and lessons." Thermal Engineering 56, no. 5 (May 2009): 432–36. http://dx.doi.org/10.1134/s0040601509050139.

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32

Srivastava, A., A. D. Contractor, H. G. Lele, and K. K. Vaze. "Tarapur atomic power station: analysis of station blackout scenario." Kerntechnik 80, no. 1 (March 17, 2015): 13–19. http://dx.doi.org/10.3139/124.110348.

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33

Ando, Yoshio. "Nuclear power in China — the first atomic power station under construction." Welding International 1, no. 10 (January 1987): 969–75. http://dx.doi.org/10.1080/09507118709449047.

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34

Ševeček, Martin, Mojmír Valach, and Chih-Hao Lee. "THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS." Acta Polytechnica CTU Proceedings 28 (December 1, 2020): 32–41. http://dx.doi.org/10.14311/app.2020.28.0032.

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State Office for Nuclear Safety is a regulator body in the Czech Republic handling also licensing of storage and transportation casks (SCs) of the spent nuclear fuel (SNF). One of the main concerns for the dry storage of SNF is the safe removal of the residual heat resulting from the decay of fission products, actinides, and activated construction materials. There are many storage systems in use around the world with different storage configuration, fuel designs and boundary conditions that need to be evaluated. Two thermal models of SNF storage casks CASTOR 440/84 and CASTOR 440/84M were developed using the COBRA-SFS code, which is an internationally accepted and validated code used for licensing of dry storage casks and safety evaluation. The casks are in operation at the Nuclear Power Plant Dukovany for dry storage of the WWER-440 SNF. Both models were validated and used for evaluation of several problems in different configuration and particularly for licensing purposes at the SUJB.
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35

Volkanovski, Andrija, and Andrej Prošek. "Delayed Station Blackout Event and Nuclear Safety." Science and Technology of Nuclear Installations 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/192601.

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The loss of off-site power (LOOP) event occurs when all electrical power to the nuclear power plant from the power grid is lost. Complete failure of both off-site and on-site alternating current (AC) power sources is referred to as a station blackout (SBO). Combined LOOP and SBO events are analyzed in this paper. The analysis is done for different time delays between the LOOP and SBO events. Deterministic safety analysis is utilized for the assessment of the plant parameters for different time delays of the SBO event. Obtained plant parameters are used for the assessment of the probabilities of the functional events in the SBO event tree. The results show that the time delay of the SBO after the LOOP leads to a decrease of the core damage frequency (CDF) from the SBO event tree. The reduction of the CDF depends on the time delay of the SBO after the LOOP event. The results show the importance of the safety systems to operate after the plant shutdown when the decay heat is large. Small changes of the basic events importance measures are identified with the introduction of the delay of the SBO event.
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36

Dean, Richard A. "Advanced fission reactors for central station power." Journal of Fusion Energy 10, no. 3 (September 1991): 215–20. http://dx.doi.org/10.1007/bf01885457.

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37

Xiang, Fang, He Xuhong, and Zhao Bingquan. "The Performance Evaluation Research of Nuclear Power Station Operators." IFAC Proceedings Volumes 34, no. 16 (September 2001): 223–27. http://dx.doi.org/10.1016/s1474-6670(17)41529-1.

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38

Birchard, Karen. "UK nuclear power station under threat from international pressure." Lancet 355, no. 9211 (April 2000): 1250. http://dx.doi.org/10.1016/s0140-6736(05)74688-2.

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39

Chang, Yen-Chiang, and Yue Zhao. "The Fukushima Nuclear Power Station incident and marine pollution." Marine Pollution Bulletin 64, no. 5 (May 2012): 897–901. http://dx.doi.org/10.1016/j.marpolbul.2012.01.038.

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40

Deng, F., Q. Lin, R. D. Zhou, W. L. Chen, and Z. D. Chen. "Radioactivity of seawater nearby Daya Bay Nuclear Power Station." IOP Conference Series: Earth and Environmental Science 82 (August 2017): 012038. http://dx.doi.org/10.1088/1755-1315/82/1/012038.

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41

O'SULLIVAN, DERMOT A. "U.K. Chooses PWR for Next Commercial Nuclear Power Station." Chemical & Engineering News 65, no. 7 (February 16, 1987): 10–12. http://dx.doi.org/10.1021/cen-v065n007.p010.

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42

Tuan Hai, Dinh. "Management Model for Nuclear Power Station Project in Vietnam." IOP Conference Series: Materials Science and Engineering 869 (July 10, 2020): 062016. http://dx.doi.org/10.1088/1757-899x/869/6/062016.

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43

Freidin, C., and A. Krichevsky. "Prestressed concrete containment of nuclear power station with PWR." Nuclear Engineering and Design 214, no. 3 (June 2002): 173–82. http://dx.doi.org/10.1016/s0029-5493(02)00032-8.

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44

Hesketh, J. A., and J. Muscroft. "Steam Turbine Generators for Sizewell ‘B’ Nuclear Power Station." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 204, no. 3 (August 1990): 183–91. http://dx.doi.org/10.1243/pime_proc_1990_204_025_02.

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45

OGANE, Daisuke, Michihiko HIRONAGA, Mitsuyuki HIRAI, Sachio OZAKI, Koichi SATO, Yasuo SHIMIZU, and Tatsuo USUI. "Development of Decommissioning-Recycle Simulator for Nuclear Power Station." Proceedings of the National Symposium on Power and Energy Systems 2000.7 (2000): 360–65. http://dx.doi.org/10.1299/jsmepes.2000.7.360.

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46

Rich, Vera. "Training of operators needed for nuclear power station safety." Nature 329, no. 6140 (October 1987): 572. http://dx.doi.org/10.1038/329572b0.

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47

Metcalfe, M. P., and R. W. Mills. "Radiocarbon mass balance for a Magnox nuclear power station." Annals of Nuclear Energy 75 (January 2015): 665–71. http://dx.doi.org/10.1016/j.anucene.2014.08.071.

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48

Pereguda, A. I., V. E. Chekhovich, and A. K. Sukhetskii. "Reliability estimation for important nuclear power station safety equipment." Atomic Energy 73, no. 4 (October 1992): 784–88. http://dx.doi.org/10.1007/bf00750646.

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49

SATO, Tadamichi. "Decommissioning at the Tokai Power Station of Japan Atomic Power Company." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 40, no. 11 (1998): 855–60. http://dx.doi.org/10.3327/jaesj.40.855.

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50

KASAI, Shigeru, Koji OKAMOTO, and Teruo AKIZUKI. "The Research Committee of Chuetsu-Oki Earthquake Influences to Kashiwazaki-Kariwa Nuclear Power Station : Good Practice on Chuetsu-Oki Earthquake Influences of Kashiwazaki-Kariwa Nuclear Power Station(Chuetsu-Oki Earthquake Influences to Nuclear Power Station,Power and Energy System Symposium)." Transactions of the Japan Society of Mechanical Engineers Series B 75, no. 751 (2009): 456–57. http://dx.doi.org/10.1299/kikaib.75.751_456.

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