Artículos de revistas sobre el tema "Best-Estimate code"
Crea una cita precisa en los estilos APA, MLA, Chicago, Harvard y otros
Consulte los 50 mejores artículos de revistas para su investigación sobre el tema "Best-Estimate code".
Junto a cada fuente en la lista de referencias hay un botón "Agregar a la bibliografía". Pulsa este botón, y generaremos automáticamente la referencia bibliográfica para la obra elegida en el estilo de cita que necesites: APA, MLA, Harvard, Vancouver, Chicago, etc.
También puede descargar el texto completo de la publicación académica en formato pdf y leer en línea su resumen siempre que esté disponible en los metadatos.
Explore artículos de revistas sobre una amplia variedad de disciplinas y organice su bibliografía correctamente.
Prošek, Andrej y Borut Mavko. "RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis". Science and Technology of Nuclear Installations 2010 (2010): 1–12. http://dx.doi.org/10.1155/2010/797193.
Texto completoGonfiotti, Bruno, Michela Angelucci, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci y Robert Stieglitz. "Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios". Applied Sciences 12, n.º 1 (29 de diciembre de 2021): 311. http://dx.doi.org/10.3390/app12010311.
Texto completoTakeuchi, K. y M. Y. Young. "Assessment of flooding in a best estimate thermal hydraulic code (W̱COBRA/TRAC)". Nuclear Engineering and Design 186, n.º 1-2 (noviembre de 1998): 225–55. http://dx.doi.org/10.1016/s0029-5493(98)00224-6.
Texto completoCross, A. W., D. P. DiVincenzo y B. M. Terhal. "A comparative code study for quantum fault tolerance". Quantum Information and Computation 9, n.º 7&8 (julio de 2009): 541–72. http://dx.doi.org/10.26421/qic9.7-8-1.
Texto completoFURUYA, Masahiro, Yoshihisa Nishi y Nobuyuki Ueda. "S083034 Predictability of Best-Estimate Code, TRACE for Flashing-Induced Density Wave Oscillations". Proceedings of Mechanical Engineering Congress, Japan 2012 (2012): _S083034–1—_S083034–5. http://dx.doi.org/10.1299/jsmemecj.2012._s083034-1.
Texto completoCarlos, S., F. Sanchez-Saez y S. Martorell. "Use of TRACE best estimate code to analyze spent fuel storage pools safety". Progress in Nuclear Energy 77 (noviembre de 2014): 224–38. http://dx.doi.org/10.1016/j.pnucene.2014.07.008.
Texto completoVinai, Paolo, Rafael Macian-Juan y Rakesh Chawla. "A statistical methodology for quantification of uncertainty in best estimate code physical models". Annals of Nuclear Energy 34, n.º 8 (agosto de 2007): 628–40. http://dx.doi.org/10.1016/j.anucene.2007.03.003.
Texto completoPetruzzi, Alessandro, Francesco D'Auria, Tomislav Bajs, Francesc Reventos y Yassin Hassan. "International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars". Science and Technology of Nuclear Installations 2008 (2008): 1–16. http://dx.doi.org/10.1155/2008/874023.
Texto completoVileiniskis, V. y A. Kaliatka. "Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module". Kerntechnik 76, n.º 4 (agosto de 2011): 254–60. http://dx.doi.org/10.3139/124.110158.
Texto completoBousbia-Salah, Anis y Francesco D'Auria. "Use of coupled code technique for Best Estimate safety analysis of nuclear power plants". Progress in Nuclear Energy 49, n.º 1 (enero de 2007): 1–13. http://dx.doi.org/10.1016/j.pnucene.2006.10.002.
Texto completoVadi, Roozbeh y Kamran Sepanloo. "Investigation of a LOCA in a typical MTR by a novel best-estimate code". Progress in Nuclear Energy 86 (enero de 2016): 141–61. http://dx.doi.org/10.1016/j.pnucene.2015.10.013.
Texto completoAgnello, G., P. A. Di Maio, A. Bersano y F. Mascari. "Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling". Journal of Physics: Conference Series 2177, n.º 1 (1 de abril de 2022): 012023. http://dx.doi.org/10.1088/1742-6596/2177/1/012023.
Texto completoBae, Sung-Won y Bub-Dong Chung. "DEVELOPMENT OF THE MULTI-DIMENSIONAL HYDRAULIC COMPONENT FOR THE BEST ESTIMATE SYSTEM ANALYSIS CODE MARS". Nuclear Engineering and Technology 41, n.º 10 (31 de diciembre de 2009): 1347–60. http://dx.doi.org/10.5516/net.2009.41.10.1347.
Texto completoKang, Seok-Ju, Hae-Yong Jeong, Sung-Won Bae, Chi-Woong Choi, Kwi-Seok Ha y Jae-Seung Suh. "Best estimate calculation and uncertainty quantification of sodium-cooled fast reactor using MARS-LMR code". Annals of Nuclear Energy 115 (mayo de 2018): 138–53. http://dx.doi.org/10.1016/j.anucene.2018.01.033.
Texto completoSengupta, Samiran, Vijay K. Veluri, R. Patel, S. Mammen y S. Bhattacharya. "Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor". Life Cycle Reliability and Safety Engineering 6, n.º 2 (junio de 2017): 109–17. http://dx.doi.org/10.1007/s41872-017-0011-y.
Texto completoGlaeser, Horst. "GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications". Science and Technology of Nuclear Installations 2008 (2008): 1–7. http://dx.doi.org/10.1155/2008/798901.
Texto completoJeong, Hae-Yong. "Analysis of Loss of Condenser Vacuum Accident using a Conservative Approach with a Best-Estimate Code". Journal of Energy Engineering 24, n.º 4 (31 de diciembre de 2015): 175–82. http://dx.doi.org/10.5855/energy.2015.24.4.175.
Texto completoLim, Chul-Kyu, Sang-Koo Han, Sook-Kwan Kim, Dong-Sik Jin, Bong-Jin Ko, Yong-Ho Hong, Kwang-Il Ahn et al. "Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code". Nuclear Engineering and Design 359 (abril de 2020): 110452. http://dx.doi.org/10.1016/j.nucengdes.2019.110452.
Texto completoCeuca, Cristian Sabin, H. Austregesilo y R. Macian-Juan. "BEST-ESTIMATE SIMULATIONS OF CONDENSATION-INDUCED WATER HAMMER IN HORIZONTAL PIPES WITH THE SYSTEM ANALYSIS CODE ATHLET". Multiphase Science and Technology 26, n.º 4 (2014): 305–27. http://dx.doi.org/10.1615/multscientechn.v26.i4.30.
Texto completoMarao, A., T. Kaliatka, A. Kaliatka y E. Ušpuras. "Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach". Kerntechnik 75, n.º 3 (abril de 2010): 72–80. http://dx.doi.org/10.3139/124.110069.
Texto completoKim, Kyung-Doo, Jae-Jun Jeong, Seung-Wook Lee, Myeong-Soo Lee, Jae-Seung Suh, Jin-Hyuk Hong y Yong-Kwan Lee. "Development of NSSS Thermal-Hydraulic Model for KNPEC-2 Simulator Using the Best-Estimate Code RETRAN-3D". Nuclear Technology 148, n.º 1 (octubre de 2004): 3–11. http://dx.doi.org/10.13182/nt04-a3543.
Texto completoTAKIWAKI, Kenya, Yutaka TAKEUCHI, Norio SAKAI y Taku KITAMURA. "A205 Development of BOP models for best estimate transient analysis code and application to plant cycle evaluation". Proceedings of the National Symposium on Power and Energy Systems 2011.16 (2011): 225–26. http://dx.doi.org/10.1299/jsmepes.2011.16.225.
Texto completoHadjam, Ahmed, Ferhat Souidi, Ahcene Loubar y Marcel Weber. "Simulation of a LBLOCA in the CALLISTO test facility using the best estimate computer code RELAP5/SCDAP3.2". Nuclear Engineering and Design 262 (septiembre de 2013): 153–67. http://dx.doi.org/10.1016/j.nucengdes.2013.03.052.
Texto completoTaleyarkhan, R. P., A. F. McFarlane, R. T. Lahey y M. Z. Podowski. "Benchmarking and qualification of the nufreq-npw code for best estimate prediction of multichannel core stability margins". Nuclear Engineering and Design 151, n.º 1 (noviembre de 1994): 157–71. http://dx.doi.org/10.1016/0029-5493(94)90040-x.
Texto completoAvramova, M., A. Velazquez-Lozada y A. Rubin. "Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database". Science and Technology of Nuclear Installations 2013 (2013): 1–12. http://dx.doi.org/10.1155/2013/725687.
Texto completoAdorni, Martina, Alessandro Del Nevo, Francesco D'Auria y Oscar Mazzantini. "A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP". Science and Technology of Nuclear Installations 2011 (2011): 1–11. http://dx.doi.org/10.1155/2011/929358.
Texto completoMathis, Alexander, Andreas V. M. Herz y Martin Stemmler. "Optimal Population Codes for Space: Grid Cells Outperform Place Cells". Neural Computation 24, n.º 9 (septiembre de 2012): 2280–317. http://dx.doi.org/10.1162/neco_a_00319.
Texto completoDUONG, Thanh Tung y Yuichi OTSUKA. "Development of Statistical Safety Analysis for Best-Estimate Code for Loss of Coolant Accident Using Relap5/Mod 3.3". Proceedings of Conference of Hokuriku-Shinetsu Branch 2020.57 (2020): D013. http://dx.doi.org/10.1299/jsmehs.2020.57.d013.
Texto completoProšek, Andrej y Marko Matkovič. "RELAP5/MOD3.3 Analysis of the Loss of External Power Event with Safety Injection Actuation". Science and Technology of Nuclear Installations 2018 (2018): 1–14. http://dx.doi.org/10.1155/2018/6964946.
Texto completoSkrzypek, M., E. Skrzypek, M. Stempniewicz y J. Malesa. "Study on the DLOFC accident of the GEMINI+ conceptual design of HTGR reactor with MELCOR and SPECTRA". Journal of Physics: Conference Series 2048, n.º 1 (1 de octubre de 2021): 012043. http://dx.doi.org/10.1088/1742-6596/2048/1/012043.
Texto completoFrepoli, Cesare. "An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model". Science and Technology of Nuclear Installations 2008 (2008): 1–15. http://dx.doi.org/10.1155/2008/498737.
Texto completoPerin, Yann y Javier Jimenez Escalante. "Application of the best-estimate plus uncertainty approach on a BWR ATWS transient using the NURESIM European code platform". Nuclear Engineering and Design 321 (septiembre de 2017): 48–56. http://dx.doi.org/10.1016/j.nucengdes.2017.05.018.
Texto completoShamir, Maoz. "The Scaling of Winner-Takes-All Accuracy with Population Size". Neural Computation 18, n.º 11 (noviembre de 2006): 2719–29. http://dx.doi.org/10.1162/neco.2006.18.11.2719.
Texto completoPetruzzi, Alessandro y Francesco D'Auria. "Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Thermal-Hydraulic System Codes". Science and Technology of Nuclear Installations 2008 (2008): 1–17. http://dx.doi.org/10.1155/2008/325071.
Texto completoKhedr, Ahmed, Martina Adorni y Francesco d’Auria. "The effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios". Nuclear Technology and Radiation Protection 20, n.º 1 (2005): 16–22. http://dx.doi.org/10.2298/ntrp0501016k.
Texto completoAngelucci, Michela, Bruno Gonfiotti, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci y Robert Stieglitz. "Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code". Applied Sciences 12, n.º 1 (24 de diciembre de 2021): 187. http://dx.doi.org/10.3390/app12010187.
Texto completoHamad, Ahmed A., Mohammed Taih Gatte y Laith Ali Abdul-Rahaim. "Efficient systematic turbo polar decoding based on optimized scaling factor and early termination mechanism". International Journal of Electrical and Computer Engineering (IJECE) 13, n.º 1 (1 de febrero de 2023): 629. http://dx.doi.org/10.11591/ijece.v13i1.pp629-637.
Texto completoWłostowski, Mateusz, Paweł Domitr y Piotr Darnowski. "A Sensitivity Study of Critical Flow Modeling with MELCOR 2.2 Code Based on the Marviken CFT-21 Experiment". Energies 14, n.º 16 (13 de agosto de 2021): 4985. http://dx.doi.org/10.3390/en14164985.
Texto completoProšek, Andrej. "RELAP5 Calculations of Bethsy 9.1b Test". Science and Technology of Nuclear Installations 2012 (2012): 1–11. http://dx.doi.org/10.1155/2012/238090.
Texto completoJones, D. P. y J. E. Holliday. "Elastic-Plastic Analysis of the PVRC Burst Disk Tests With Comparison to the ASME Code Primary Stress Limits". Journal of Pressure Vessel Technology 122, n.º 2 (7 de marzo de 2000): 146–51. http://dx.doi.org/10.1115/1.556164.
Texto completoWong, C. M. y W. K. Tso. "Seismic loading for buildings with setbacks". Canadian Journal of Civil Engineering 21, n.º 5 (1 de octubre de 1994): 863–71. http://dx.doi.org/10.1139/l94-092.
Texto completoAntariksawan, Anhar Riza, Surip Widodo y Hendro Tjahjono. "PARAMETRIC STUDY OF LOCA IN TRIGA-2000 USING RELAP5/SCDAP CODE". JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 19, n.º 2 (26 de mayo de 2017): 59. http://dx.doi.org/10.17146/tdm.2017.19.2.3279.
Texto completoUi, Atsushi y Takamasa Miyaji. "Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System". Nuclear Science and Engineering 148, n.º 2 (octubre de 2004): 281–90. http://dx.doi.org/10.13182/nse04-a2458.
Texto completoJin, Dong-Sik, Sook-Kwan Kim, Sang-Koo Han, Chul-Kyu Lim, Bong-Jin Ko, Yong-Ho Hong, Kwang-Il Ahn et al. "Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code". Nuclear Engineering and Design 358 (marzo de 2020): 110443. http://dx.doi.org/10.1016/j.nucengdes.2019.110443.
Texto completoPošta, Borna y Siniša Šadek. "Mathematical model of the NPP Krško PCFV system for the RELAP5 computer code". Journal of Energy - Energija 66, n.º 1-4 (23 de junio de 2022): 226–40. http://dx.doi.org/10.37798/2017661-4106.
Texto completoRacca, Stefano y Tomasz Kozlowski. "Trace Code Validation for BWR Spray Cooling Injection and CCFL Condition Based on GÖTA Facility Experiments". Science and Technology of Nuclear Installations 2012 (2012): 1–17. http://dx.doi.org/10.1155/2012/282987.
Texto completoTong, Michael T., Ian Halliwell y Louis J. Ghosn. "A Computer Code for Gas Turbine Engine Weight and Disk Life Estimation". Journal of Engineering for Gas Turbines and Power 126, n.º 2 (1 de abril de 2004): 265–70. http://dx.doi.org/10.1115/1.1691980.
Texto completoMartin, Robert P. y Larry D. O'Dell. "Development Considerations of AREVA NP Inc.'s Realistic LBLOCA Analysis Methodology". Science and Technology of Nuclear Installations 2008 (2008): 1–13. http://dx.doi.org/10.1155/2008/239718.
Texto completoEbiwonjumi, Bamidele, Peng Zhang y Deokjung Lee. "SENSITIVITY ANALYSIS OF PWR SPENT FUEL DUE TO MODELLING PARAMETER UNCERTAINTIES USING SURROGATE MODELS". EPJ Web of Conferences 247 (2021): 15009. http://dx.doi.org/10.1051/epjconf/202124715009.
Texto completoZhou, Lin, Qingsheng Zhao, Shukai Chi, Yanlong Li, Lanjun Liu y Qianxiang Yu. "A fractional Fourier transform–based channel estimation algorithm in single-carrier direct sequence code division multiple access underwater acoustic communication system". International Journal of Distributed Sensor Networks 15, n.º 1 (enero de 2019): 155014771982600. http://dx.doi.org/10.1177/1550147719826001.
Texto completo