Artículos de revistas sobre el tema "European Pressurized Reactor"
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Leny, J. C. "The European Pressurized Water Reactor / Der Europäische Druckwasserreaktor." Kerntechnik 58, n.º 6 (1 de junio de 1993): 353–57. http://dx.doi.org/10.1515/kern-1993-580615.
Texto completoCzech, J., J. Wirkner, M. Yvon, M. Serret, U. Krugmann, K. E. Schmidt, J. P. Berger y M. Grenet. "European pressurized water reactor: safety objectives and principles". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 25–32. http://dx.doi.org/10.1016/s0029-5493(98)00255-6.
Texto completoBaumgartl, B. J. y F. Bouteille. "The European Pressurized Water Reactor (EPR): an advanced PWR". Revue Générale Nucléaire, n.º 6 (noviembre de 1994): 478–83. http://dx.doi.org/10.1051/rgn/19946478.
Texto completoBonhomme, Nico. "Systems organization for the European pressurized water reactor (EPR)". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 71–78. http://dx.doi.org/10.1016/s0029-5493(98)00258-1.
Texto completoQuinot, P. y G. Desfontaines. "The main components of the European pressurized water reactor". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 121–33. http://dx.doi.org/10.1016/s0029-5493(98)00261-1.
Texto completoTeichel, Holger. "Objectives in developing the European pressurized water reactor (EPR)". Nuclear Engineering and Design 165, n.º 1-2 (agosto de 1996): 271–76. http://dx.doi.org/10.1016/0029-5493(95)01158-7.
Texto completoValenti, Michael. "A Next-Generation Reactor". Mechanical Engineering 120, n.º 08 (1 de agosto de 1998): 68–71. http://dx.doi.org/10.1115/1.1998-aug-5.
Texto completoSkrzypek, Maciej y R. Laskowski. "Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code". Nukleonika 60, n.º 3 (1 de septiembre de 2015): 537–44. http://dx.doi.org/10.1515/nuka-2015-0110.
Texto completoYan, Jia-chuan, Xiao-fei Jin, Feng Qin, Zheng Li, Feng Fan y Jin-ping Ou. "Modular construction mechanics of a European pressurized reactor steel containment liner". Journal of Zhejiang University-SCIENCE A 18, n.º 6 (junio de 2017): 467–86. http://dx.doi.org/10.1631/jzus.a1600136.
Texto completoBury, Tomasz. "Evaluation of passive autocatalytic recombiners operation efficiency by means of the lumped parameter approach". Nukleonika 60, n.º 2 (1 de junio de 2015): 339–45. http://dx.doi.org/10.1515/nuka-2015-0042.
Texto completoLago, Daniel y Farzad Rahnema. "Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem". Progress in Nuclear Energy 93 (noviembre de 2016): 18–46. http://dx.doi.org/10.1016/j.pnucene.2016.07.009.
Texto completoEbbesmeyer, Peter, Ju¨rgen Gausemeier, Holger Krumm, Thorsten Molt y Thomas Gruß. "Virtual Web Plant: An Internet-Based Plant Engineering Information System". Journal of Computing and Information Science in Engineering 1, n.º 3 (1 de junio de 2001): 257–60. http://dx.doi.org/10.1115/1.1405155.
Texto completoAbrefah, Rex, Prince Atsu y Robert Sogbadji. "Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code". Nuclear Technology and Radiation Protection 34, n.º 3 (2019): 238–42. http://dx.doi.org/10.2298/ntrp190108029a.
Texto completoDing, Yongjian. "Schutzzielorientiertes Design der Sicherheitsleittechnik". atp magazin 56, n.º 05 (28 de abril de 2014): 54–61. http://dx.doi.org/10.17560/atp.v56i05.2248.
Texto completoFischer, Manfred. "ICONE11-36196 Severe accident mitigation and core melt retention in the European Pressurized Reactor (EPR)". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2003 (2003): 151. http://dx.doi.org/10.1299/jsmeicone.2003.151.
Texto completoVignon, Dominique. "Franco-German nuclear cooperation: from the ‘common product’ to the first European pressurized water reactor". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 1–3. http://dx.doi.org/10.1016/s0029-5493(98)00292-1.
Texto completoDu Toit, Maria Hendrina y Vishana Vivian Naicker. "Developing a Full-Core MCNP6 and RELAP5 Model of the European Pressurized Reactor Using NWURCS". Nuclear Science and Engineering 191, n.º 3 (9 de julio de 2018): 291–304. http://dx.doi.org/10.1080/00295639.2018.1468153.
Texto completoSimons, A. y C. Bauer. "Life cycle assessment of the European pressurized reactor and the influence of different fuel cycle strategies". Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 226, n.º 3 (14 de marzo de 2012): 427–44. http://dx.doi.org/10.1177/0957650912440549.
Texto completoJiang, Jin-yang, Ying-jun Yu, Hong-yan Chu, Wei Sun y Yun Gao. "Influence of Concrete Properties on Molten Core-Concrete Interaction: A Simulation Study". Advances in Materials Science and Engineering 2016 (2016): 1–10. http://dx.doi.org/10.1155/2016/5380835.
Texto completoQi, Shuang, Wenxin Xiang, Lixun Cai, Xiaokun Liu, Yonggang Wang, Fangmao Ning, Lei Qi, Weiwei Yu y Jinhua Shi. "Study on Micro-Structure and Tensile Mechanical Properties of Dissimilar Metal Weld Joint Connecting Steam Generator Nozzle and Safe-End". Crystals 11, n.º 12 (26 de noviembre de 2021): 1470. http://dx.doi.org/10.3390/cryst11121470.
Texto completoFischer, U. "The European pressurized water reactor Result of the French–German cooperation of experienced NPP suppliers and operators". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 15–23. http://dx.doi.org/10.1016/s0029-5493(98)00254-4.
Texto completoEglin, Wolfgang, Ulrich Krugmann, Horst A. Weisshäupl y Werner Scholtyssek. "Assessment of the Severe Accident Mitigation Features of the European Pressurized Water Reactor by Cooperative Research and Development". Nuclear Technology 126, n.º 2 (mayo de 1999): 143–52. http://dx.doi.org/10.13182/nt99-a2963.
Texto completoLucas, D., D. Bestion, E. Bodèle, P. Coste, M. Scheuerer, F. D'Auria, D. Mazzini et al. "An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project". Science and Technology of Nuclear Installations 2009 (2009): 1–13. http://dx.doi.org/10.1155/2009/583259.
Texto completoNakata, Alexandre Ezzidi, Masanori Naitoh y Chris Allison. "NEED OF A NEXT GENERATION SEVERE ACCIDENT CODE". JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 21, n.º 3 (12 de noviembre de 2019): 119. http://dx.doi.org/10.17146/tdm.2019.21.3.5630.
Texto completoBassi, C. y M. Marques. "Reliability Assessment of 2400 MWth Gas-Cooled Fast Reactor Natural Circulation Decay Heat Removal in Pressurized Situations". Science and Technology of Nuclear Installations 2008 (2008): 1–16. http://dx.doi.org/10.1155/2008/287376.
Texto completoFischer, Manfred. "The severe accident mitigation concept and the design measures for core melt retention of the European Pressurized Reactor (EPR)". Nuclear Engineering and Design 230, n.º 1-3 (mayo de 2004): 169–80. http://dx.doi.org/10.1016/j.nucengdes.2003.11.034.
Texto completoCurca-Tivig, Florin. "Emergency Core Cooling Mode of the European Pressurized Water Reactor: The Evolution from Combined Injection to Cold-Leg Injection". Nuclear Technology 124, n.º 1 (octubre de 1998): 65–81. http://dx.doi.org/10.13182/nt98-a2909.
Texto completodu Toit, Maria Hendrina y Vishana Vivian Naicker. "Neutronic design of homogeneous thorium/uranium fuel for 24 month fuel cycles in the European pressurized reactor using MCNP6". Nuclear Engineering and Design 337 (octubre de 2018): 394–405. http://dx.doi.org/10.1016/j.nucengdes.2018.07.023.
Texto completoGross, Maximilian, Faisal Sedeqi, Diana-María Amaya-Dueñas, Marc P. Heddrich y S. Asif Ansar. "Characterisation of a 10-Layer SOC Stack Under Pressurised CO2 Electrolysis Operation". ECS Meeting Abstracts MA2022-02, n.º 49 (9 de octubre de 2022): 1950. http://dx.doi.org/10.1149/ma2022-02491950mtgabs.
Texto completoTerzuoli, F., M. C. Galassi, D. Mazzini y F. D'Auria. "CFD Code Validation against Stratified Air-Water Flow Experimental Data". Science and Technology of Nuclear Installations 2008 (2008): 1–7. http://dx.doi.org/10.1155/2008/434212.
Texto completoCiurluini, Cristiano, Fabio Giannetti, Alessandro Del Nevo y Gianfranco Caruso. "Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category". Energies 14, n.º 6 (11 de marzo de 2021): 1541. http://dx.doi.org/10.3390/en14061541.
Texto completoLamirand, Vincent, Pavel Frajtag, Daniel Godat, Oskari Pakari, Axel Laureau, Adolfo Rais, Mathieu Hursin, Grégory Hursin, Carlo Fiorina y Andreas Pautz. "The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator". EPJ Web of Conferences 225 (2020): 04020. http://dx.doi.org/10.1051/epjconf/202022504020.
Texto completoChu, Hong Yan, Jin Yang Jiang, Wei Sun y Ming Zhong Zhang. "Mechanical Properties and Damage Evolution of Siliceous Concrete Subjected to Elevated Temperatures". Key Engineering Materials 711 (septiembre de 2016): 488–95. http://dx.doi.org/10.4028/www.scientific.net/kem.711.488.
Texto completoVeres, Mihály, Ede Hertelendi, György Uchrin, Eszter Csaba, István Barnabás, Péter Ormai, Gábor Volent y István Futó. "Concentration of Radiocarbon and Its Chemical Forms in Gaseous Effluents, Environmental Air, Nuclear Waste and Primary Water of a Pressurized Water Reactor Power Plant in Hungary". Radiocarbon 37, n.º 2 (1995): 497–504. http://dx.doi.org/10.1017/s0033822200030976.
Texto completoŠadek, Siniša, Davor Grgić y Zdenko Šimić. "Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems". Science and Technology of Nuclear Installations 2017 (2017): 1–16. http://dx.doi.org/10.1155/2017/8431934.
Texto completoCheymol, G., L. Maurin, L. Remy, V. Arounassalame, H. Maskrot, S. Rougeault, V. Dauvois et al. "Tests under irradiation of optical fibers and cables devoted to corium monitoring in case of severe accident in a Nuclear Power Plant". EPJ Web of Conferences 225 (2020): 08006. http://dx.doi.org/10.1051/epjconf/202022508006.
Texto completoDolan, P. y A. Dolan. "A review of the European pressurised water reactor (EPR)". Nuclear Energy 43, n.º 4 (2004): 205–8. http://dx.doi.org/10.1680/nuen.43.4.205.41193.
Texto completoTeichel, Holger y Xavier Pouget-Abadie. "How the European Pressurised Water Reactor fulfils the utility requirements". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 9–13. http://dx.doi.org/10.1016/s0029-5493(98)00253-2.
Texto completoMaillart, Hervé. "Design of the I&C for the European pressurised water reactor". Nuclear Engineering and Design 187, n.º 1 (enero de 1999): 135–41. http://dx.doi.org/10.1016/s0029-5493(98)00260-x.
Texto completoPomponi, Francesco y Jim Hart. "The greenhouse gas emissions of nuclear energy – Life cycle assessment of a European pressurised reactor". Applied Energy 290 (mayo de 2021): 116743. http://dx.doi.org/10.1016/j.apenergy.2021.116743.
Texto completoBoettcher, Agnieszka y Zuzanna Marcinkowska. "Influence of accident tolerant fuel cladding material on the European pressurised reactor core neutronic characteristics". Annals of Nuclear Energy 119 (septiembre de 2018): 203–13. http://dx.doi.org/10.1016/j.anucene.2018.05.001.
Texto completoAddabbo, Carmelo y Alessandro Annunziato. "The LOBI Integral System Test Facility Experimental Programme". Science and Technology of Nuclear Installations 2012 (2012): 1–16. http://dx.doi.org/10.1155/2012/238019.
Texto completoLi, Jinfeng. "Computing Benchmark of Gadolinium-bearing Fuel Pins’ Depletion Skin Effect based on Deterministic and Monte Carlo Methods". Annals of Emerging Technologies in Computing 5, n.º 1 (1 de enero de 2021): 1–12. http://dx.doi.org/10.33166/aetic.2021.01.001.
Texto completoKronenberg, J. "Uncertainty and sensitivity analysis with respect to the hydrogen production determined by MELCOR 1.8.4 code during a severe accident". Kerntechnik 66, n.º 4 (1 de agosto de 2001): 171–76. http://dx.doi.org/10.1515/kern-2001-0075.
Texto completo"Defects found in European Pressurized Water Reactor". Physics Today, 2008. http://dx.doi.org/10.1063/pt.5.022126.
Texto completoVukolova, Angelina-Nataliya V. y Andrei A. Rusinkevich. "Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities". Journal of Nuclear Engineering and Radiation Science 7, n.º 1 (1 de octubre de 2020). http://dx.doi.org/10.1115/1.4047044.
Texto completo"00/03305 Optimized conventional island design for the European pressurized water reactor (EPR)". Fuel and Energy Abstracts 41, n.º 6 (noviembre de 2000): 372. http://dx.doi.org/10.1016/s0140-6701(00)94379-0.
Texto completoAbarca, A., R. Miró, G. Verdú y J. A. Bermejo. "Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code". Journal of Nuclear Engineering and Radiation Science 2, n.º 2 (29 de febrero de 2016). http://dx.doi.org/10.1115/1.4031660.
Texto completoKatsuyama, Jinya, Kazuya Osakabe, Shumpei Uno, Yinsheng Li y Shinobu Yoshimura. "Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels". Journal of Pressure Vessel Technology 142, n.º 2 (24 de febrero de 2020). http://dx.doi.org/10.1115/1.4045874.
Texto completoStraetz, Marcel, Joerg Starflinger, Rainer Mertz y Dieter Brillert. "Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 as Working Fluid". Journal of Nuclear Engineering and Radiation Science 5, n.º 1 (1 de enero de 2019). http://dx.doi.org/10.1115/1.4039884.
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