Статті в журналах з теми "European Pressurized Reactor"
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Leny, J. C. "The European Pressurized Water Reactor / Der Europäische Druckwasserreaktor." Kerntechnik 58, no. 6 (June 1, 1993): 353–57. http://dx.doi.org/10.1515/kern-1993-580615.
Повний текст джерелаCzech, J., J. Wirkner, M. Yvon, M. Serret, U. Krugmann, K. E. Schmidt, J. P. Berger, and M. Grenet. "European pressurized water reactor: safety objectives and principles." Nuclear Engineering and Design 187, no. 1 (January 1999): 25–32. http://dx.doi.org/10.1016/s0029-5493(98)00255-6.
Повний текст джерелаBaumgartl, B. J., and F. Bouteille. "The European Pressurized Water Reactor (EPR): an advanced PWR." Revue Générale Nucléaire, no. 6 (November 1994): 478–83. http://dx.doi.org/10.1051/rgn/19946478.
Повний текст джерелаBonhomme, Nico. "Systems organization for the European pressurized water reactor (EPR)." Nuclear Engineering and Design 187, no. 1 (January 1999): 71–78. http://dx.doi.org/10.1016/s0029-5493(98)00258-1.
Повний текст джерелаQuinot, P., and G. Desfontaines. "The main components of the European pressurized water reactor." Nuclear Engineering and Design 187, no. 1 (January 1999): 121–33. http://dx.doi.org/10.1016/s0029-5493(98)00261-1.
Повний текст джерелаTeichel, Holger. "Objectives in developing the European pressurized water reactor (EPR)." Nuclear Engineering and Design 165, no. 1-2 (August 1996): 271–76. http://dx.doi.org/10.1016/0029-5493(95)01158-7.
Повний текст джерелаValenti, Michael. "A Next-Generation Reactor." Mechanical Engineering 120, no. 08 (August 1, 1998): 68–71. http://dx.doi.org/10.1115/1.1998-aug-5.
Повний текст джерелаSkrzypek, Maciej, and R. Laskowski. "Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code." Nukleonika 60, no. 3 (September 1, 2015): 537–44. http://dx.doi.org/10.1515/nuka-2015-0110.
Повний текст джерелаYan, Jia-chuan, Xiao-fei Jin, Feng Qin, Zheng Li, Feng Fan, and Jin-ping Ou. "Modular construction mechanics of a European pressurized reactor steel containment liner." Journal of Zhejiang University-SCIENCE A 18, no. 6 (June 2017): 467–86. http://dx.doi.org/10.1631/jzus.a1600136.
Повний текст джерелаBury, Tomasz. "Evaluation of passive autocatalytic recombiners operation efficiency by means of the lumped parameter approach." Nukleonika 60, no. 2 (June 1, 2015): 339–45. http://dx.doi.org/10.1515/nuka-2015-0042.
Повний текст джерелаLago, Daniel, and Farzad Rahnema. "Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem." Progress in Nuclear Energy 93 (November 2016): 18–46. http://dx.doi.org/10.1016/j.pnucene.2016.07.009.
Повний текст джерелаEbbesmeyer, Peter, Ju¨rgen Gausemeier, Holger Krumm, Thorsten Molt, and Thomas Gruß. "Virtual Web Plant: An Internet-Based Plant Engineering Information System." Journal of Computing and Information Science in Engineering 1, no. 3 (June 1, 2001): 257–60. http://dx.doi.org/10.1115/1.1405155.
Повний текст джерелаAbrefah, Rex, Prince Atsu, and 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, no. 3 (2019): 238–42. http://dx.doi.org/10.2298/ntrp190108029a.
Повний текст джерелаDing, Yongjian. "Schutzzielorientiertes Design der Sicherheitsleittechnik." atp magazin 56, no. 05 (April 28, 2014): 54–61. http://dx.doi.org/10.17560/atp.v56i05.2248.
Повний текст джерелаFischer, 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.
Повний текст джерелаVignon, Dominique. "Franco-German nuclear cooperation: from the ‘common product’ to the first European pressurized water reactor." Nuclear Engineering and Design 187, no. 1 (January 1999): 1–3. http://dx.doi.org/10.1016/s0029-5493(98)00292-1.
Повний текст джерелаDu Toit, Maria Hendrina, and Vishana Vivian Naicker. "Developing a Full-Core MCNP6 and RELAP5 Model of the European Pressurized Reactor Using NWURCS." Nuclear Science and Engineering 191, no. 3 (July 9, 2018): 291–304. http://dx.doi.org/10.1080/00295639.2018.1468153.
Повний текст джерелаSimons, A., and 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, no. 3 (March 14, 2012): 427–44. http://dx.doi.org/10.1177/0957650912440549.
Повний текст джерелаJiang, Jin-yang, Ying-jun Yu, Hong-yan Chu, Wei Sun, and 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.
Повний текст джерелаQi, Shuang, Wenxin Xiang, Lixun Cai, Xiaokun Liu, Yonggang Wang, Fangmao Ning, Lei Qi, Weiwei Yu, and Jinhua Shi. "Study on Micro-Structure and Tensile Mechanical Properties of Dissimilar Metal Weld Joint Connecting Steam Generator Nozzle and Safe-End." Crystals 11, no. 12 (November 26, 2021): 1470. http://dx.doi.org/10.3390/cryst11121470.
Повний текст джерелаFischer, U. "The European pressurized water reactor Result of the French–German cooperation of experienced NPP suppliers and operators." Nuclear Engineering and Design 187, no. 1 (January 1999): 15–23. http://dx.doi.org/10.1016/s0029-5493(98)00254-4.
Повний текст джерелаEglin, Wolfgang, Ulrich Krugmann, Horst A. Weisshäupl, and Werner Scholtyssek. "Assessment of the Severe Accident Mitigation Features of the European Pressurized Water Reactor by Cooperative Research and Development." Nuclear Technology 126, no. 2 (May 1999): 143–52. http://dx.doi.org/10.13182/nt99-a2963.
Повний текст джерелаLucas, 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.
Повний текст джерелаNakata, Alexandre Ezzidi, Masanori Naitoh, and Chris Allison. "NEED OF A NEXT GENERATION SEVERE ACCIDENT CODE." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 21, no. 3 (November 12, 2019): 119. http://dx.doi.org/10.17146/tdm.2019.21.3.5630.
Повний текст джерелаBassi, C., and 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.
Повний текст джерелаFischer, 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, no. 1-3 (May 2004): 169–80. http://dx.doi.org/10.1016/j.nucengdes.2003.11.034.
Повний текст джерелаCurca-Tivig, Florin. "Emergency Core Cooling Mode of the European Pressurized Water Reactor: The Evolution from Combined Injection to Cold-Leg Injection." Nuclear Technology 124, no. 1 (October 1998): 65–81. http://dx.doi.org/10.13182/nt98-a2909.
Повний текст джерелаdu Toit, Maria Hendrina, and 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 (October 2018): 394–405. http://dx.doi.org/10.1016/j.nucengdes.2018.07.023.
Повний текст джерелаGross, Maximilian, Faisal Sedeqi, Diana-María Amaya-Dueñas, Marc P. Heddrich, and S. Asif Ansar. "Characterisation of a 10-Layer SOC Stack Under Pressurised CO2 Electrolysis Operation." ECS Meeting Abstracts MA2022-02, no. 49 (October 9, 2022): 1950. http://dx.doi.org/10.1149/ma2022-02491950mtgabs.
Повний текст джерелаTerzuoli, F., M. C. Galassi, D. Mazzini, and 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.
Повний текст джерелаCiurluini, Cristiano, Fabio Giannetti, Alessandro Del Nevo, and Gianfranco Caruso. "Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category." Energies 14, no. 6 (March 11, 2021): 1541. http://dx.doi.org/10.3390/en14061541.
Повний текст джерелаLamirand, Vincent, Pavel Frajtag, Daniel Godat, Oskari Pakari, Axel Laureau, Adolfo Rais, Mathieu Hursin, Grégory Hursin, Carlo Fiorina, and 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.
Повний текст джерелаChu, Hong Yan, Jin Yang Jiang, Wei Sun, and Ming Zhong Zhang. "Mechanical Properties and Damage Evolution of Siliceous Concrete Subjected to Elevated Temperatures." Key Engineering Materials 711 (September 2016): 488–95. http://dx.doi.org/10.4028/www.scientific.net/kem.711.488.
Повний текст джерелаVeres, Mihály, Ede Hertelendi, György Uchrin, Eszter Csaba, István Barnabás, Péter Ormai, Gábor Volent, and 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, no. 2 (1995): 497–504. http://dx.doi.org/10.1017/s0033822200030976.
Повний текст джерелаŠadek, Siniša, Davor Grgić, and 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.
Повний текст джерелаCheymol, 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.
Повний текст джерелаDolan, P., and A. Dolan. "A review of the European pressurised water reactor (EPR)." Nuclear Energy 43, no. 4 (2004): 205–8. http://dx.doi.org/10.1680/nuen.43.4.205.41193.
Повний текст джерелаTeichel, Holger, and Xavier Pouget-Abadie. "How the European Pressurised Water Reactor fulfils the utility requirements." Nuclear Engineering and Design 187, no. 1 (January 1999): 9–13. http://dx.doi.org/10.1016/s0029-5493(98)00253-2.
Повний текст джерелаMaillart, Hervé. "Design of the I&C for the European pressurised water reactor." Nuclear Engineering and Design 187, no. 1 (January 1999): 135–41. http://dx.doi.org/10.1016/s0029-5493(98)00260-x.
Повний текст джерелаPomponi, Francesco, and Jim Hart. "The greenhouse gas emissions of nuclear energy – Life cycle assessment of a European pressurised reactor." Applied Energy 290 (May 2021): 116743. http://dx.doi.org/10.1016/j.apenergy.2021.116743.
Повний текст джерелаBoettcher, Agnieszka, and Zuzanna Marcinkowska. "Influence of accident tolerant fuel cladding material on the European pressurised reactor core neutronic characteristics." Annals of Nuclear Energy 119 (September 2018): 203–13. http://dx.doi.org/10.1016/j.anucene.2018.05.001.
Повний текст джерелаAddabbo, Carmelo, and 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.
Повний текст джерелаLi, 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, no. 1 (January 1, 2021): 1–12. http://dx.doi.org/10.33166/aetic.2021.01.001.
Повний текст джерелаKronenberg, J. "Uncertainty and sensitivity analysis with respect to the hydrogen production determined by MELCOR 1.8.4 code during a severe accident." Kerntechnik 66, no. 4 (August 1, 2001): 171–76. http://dx.doi.org/10.1515/kern-2001-0075.
Повний текст джерела"Defects found in European Pressurized Water Reactor." Physics Today, 2008. http://dx.doi.org/10.1063/pt.5.022126.
Повний текст джерелаVukolova, Angelina-Nataliya V., and 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, no. 1 (October 1, 2020). http://dx.doi.org/10.1115/1.4047044.
Повний текст джерела"00/03305 Optimized conventional island design for the European pressurized water reactor (EPR)." Fuel and Energy Abstracts 41, no. 6 (November 2000): 372. http://dx.doi.org/10.1016/s0140-6701(00)94379-0.
Повний текст джерелаAbarca, A., R. Miró, G. Verdú, and 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, no. 2 (February 29, 2016). http://dx.doi.org/10.1115/1.4031660.
Повний текст джерелаKatsuyama, Jinya, Kazuya Osakabe, Shumpei Uno, Yinsheng Li, and Shinobu Yoshimura. "Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels." Journal of Pressure Vessel Technology 142, no. 2 (February 24, 2020). http://dx.doi.org/10.1115/1.4045874.
Повний текст джерелаStraetz, Marcel, Joerg Starflinger, Rainer Mertz, and 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, no. 1 (January 1, 2019). http://dx.doi.org/10.1115/1.4039884.
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