Статті в журналах з теми "Best-Estimate code"
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Prošek, Andrej, and 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.
Повний текст джерелаGonfiotti, Bruno, Michela Angelucci, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci, and 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, no. 1 (December 29, 2021): 311. http://dx.doi.org/10.3390/app12010311.
Повний текст джерелаTakeuchi, K., and M. Y. Young. "Assessment of flooding in a best estimate thermal hydraulic code (W̱COBRA/TRAC)." Nuclear Engineering and Design 186, no. 1-2 (November 1998): 225–55. http://dx.doi.org/10.1016/s0029-5493(98)00224-6.
Повний текст джерелаCross, A. W., D. P. DiVincenzo, and B. M. Terhal. "A comparative code study for quantum fault tolerance." Quantum Information and Computation 9, no. 7&8 (July 2009): 541–72. http://dx.doi.org/10.26421/qic9.7-8-1.
Повний текст джерелаFURUYA, Masahiro, Yoshihisa Nishi, and 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.
Повний текст джерелаCarlos, S., F. Sanchez-Saez, and S. Martorell. "Use of TRACE best estimate code to analyze spent fuel storage pools safety." Progress in Nuclear Energy 77 (November 2014): 224–38. http://dx.doi.org/10.1016/j.pnucene.2014.07.008.
Повний текст джерелаVinai, Paolo, Rafael Macian-Juan, and Rakesh Chawla. "A statistical methodology for quantification of uncertainty in best estimate code physical models." Annals of Nuclear Energy 34, no. 8 (August 2007): 628–40. http://dx.doi.org/10.1016/j.anucene.2007.03.003.
Повний текст джерелаPetruzzi, Alessandro, Francesco D'Auria, Tomislav Bajs, Francesc Reventos, and 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.
Повний текст джерелаVileiniskis, V., and A. Kaliatka. "Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module." Kerntechnik 76, no. 4 (August 2011): 254–60. http://dx.doi.org/10.3139/124.110158.
Повний текст джерелаBousbia-Salah, Anis, and Francesco D'Auria. "Use of coupled code technique for Best Estimate safety analysis of nuclear power plants." Progress in Nuclear Energy 49, no. 1 (January 2007): 1–13. http://dx.doi.org/10.1016/j.pnucene.2006.10.002.
Повний текст джерелаVadi, Roozbeh, and Kamran Sepanloo. "Investigation of a LOCA in a typical MTR by a novel best-estimate code." Progress in Nuclear Energy 86 (January 2016): 141–61. http://dx.doi.org/10.1016/j.pnucene.2015.10.013.
Повний текст джерелаAgnello, G., P. A. Di Maio, A. Bersano, and F. Mascari. "Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling." Journal of Physics: Conference Series 2177, no. 1 (April 1, 2022): 012023. http://dx.doi.org/10.1088/1742-6596/2177/1/012023.
Повний текст джерелаBae, Sung-Won, and Bub-Dong Chung. "DEVELOPMENT OF THE MULTI-DIMENSIONAL HYDRAULIC COMPONENT FOR THE BEST ESTIMATE SYSTEM ANALYSIS CODE MARS." Nuclear Engineering and Technology 41, no. 10 (December 31, 2009): 1347–60. http://dx.doi.org/10.5516/net.2009.41.10.1347.
Повний текст джерелаKang, Seok-Ju, Hae-Yong Jeong, Sung-Won Bae, Chi-Woong Choi, Kwi-Seok Ha, and Jae-Seung Suh. "Best estimate calculation and uncertainty quantification of sodium-cooled fast reactor using MARS-LMR code." Annals of Nuclear Energy 115 (May 2018): 138–53. http://dx.doi.org/10.1016/j.anucene.2018.01.033.
Повний текст джерелаSengupta, Samiran, Vijay K. Veluri, R. Patel, S. Mammen, and S. Bhattacharya. "Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor." Life Cycle Reliability and Safety Engineering 6, no. 2 (June 2017): 109–17. http://dx.doi.org/10.1007/s41872-017-0011-y.
Повний текст джерелаGlaeser, 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.
Повний текст джерелаJeong, Hae-Yong. "Analysis of Loss of Condenser Vacuum Accident using a Conservative Approach with a Best-Estimate Code." Journal of Energy Engineering 24, no. 4 (December 31, 2015): 175–82. http://dx.doi.org/10.5855/energy.2015.24.4.175.
Повний текст джерелаLim, 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 (April 2020): 110452. http://dx.doi.org/10.1016/j.nucengdes.2019.110452.
Повний текст джерелаCeuca, Cristian Sabin, H. Austregesilo, and 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, no. 4 (2014): 305–27. http://dx.doi.org/10.1615/multscientechn.v26.i4.30.
Повний текст джерелаMarao, A., T. Kaliatka, A. Kaliatka, and E. Ušpuras. "Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach." Kerntechnik 75, no. 3 (April 2010): 72–80. http://dx.doi.org/10.3139/124.110069.
Повний текст джерелаKim, Kyung-Doo, Jae-Jun Jeong, Seung-Wook Lee, Myeong-Soo Lee, Jae-Seung Suh, Jin-Hyuk Hong, and Yong-Kwan Lee. "Development of NSSS Thermal-Hydraulic Model for KNPEC-2 Simulator Using the Best-Estimate Code RETRAN-3D." Nuclear Technology 148, no. 1 (October 2004): 3–11. http://dx.doi.org/10.13182/nt04-a3543.
Повний текст джерелаTAKIWAKI, Kenya, Yutaka TAKEUCHI, Norio SAKAI, and 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.
Повний текст джерелаHadjam, Ahmed, Ferhat Souidi, Ahcene Loubar, and 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 (September 2013): 153–67. http://dx.doi.org/10.1016/j.nucengdes.2013.03.052.
Повний текст джерелаTaleyarkhan, R. P., A. F. McFarlane, R. T. Lahey, and 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, no. 1 (November 1994): 157–71. http://dx.doi.org/10.1016/0029-5493(94)90040-x.
Повний текст джерелаAvramova, M., A. Velazquez-Lozada, and 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.
Повний текст джерелаAdorni, Martina, Alessandro Del Nevo, Francesco D'Auria, and 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.
Повний текст джерелаMathis, Alexander, Andreas V. M. Herz, and Martin Stemmler. "Optimal Population Codes for Space: Grid Cells Outperform Place Cells." Neural Computation 24, no. 9 (September 2012): 2280–317. http://dx.doi.org/10.1162/neco_a_00319.
Повний текст джерелаDUONG, Thanh Tung, and 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.
Повний текст джерелаProšek, Andrej, and 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.
Повний текст джерелаSkrzypek, M., E. Skrzypek, M. Stempniewicz, and 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, no. 1 (October 1, 2021): 012043. http://dx.doi.org/10.1088/1742-6596/2048/1/012043.
Повний текст джерелаFrepoli, 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.
Повний текст джерелаPerin, Yann, and 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 (September 2017): 48–56. http://dx.doi.org/10.1016/j.nucengdes.2017.05.018.
Повний текст джерелаShamir, Maoz. "The Scaling of Winner-Takes-All Accuracy with Population Size." Neural Computation 18, no. 11 (November 2006): 2719–29. http://dx.doi.org/10.1162/neco.2006.18.11.2719.
Повний текст джерелаPetruzzi, Alessandro, and 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.
Повний текст джерелаKhedr, Ahmed, Martina Adorni, and 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, no. 1 (2005): 16–22. http://dx.doi.org/10.2298/ntrp0501016k.
Повний текст джерелаAngelucci, Michela, Bruno Gonfiotti, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci, and 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, no. 1 (December 24, 2021): 187. http://dx.doi.org/10.3390/app12010187.
Повний текст джерелаHamad, Ahmed A., Mohammed Taih Gatte, and 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, no. 1 (February 1, 2023): 629. http://dx.doi.org/10.11591/ijece.v13i1.pp629-637.
Повний текст джерелаWłostowski, Mateusz, Paweł Domitr, and Piotr Darnowski. "A Sensitivity Study of Critical Flow Modeling with MELCOR 2.2 Code Based on the Marviken CFT-21 Experiment." Energies 14, no. 16 (August 13, 2021): 4985. http://dx.doi.org/10.3390/en14164985.
Повний текст джерелаProšek, 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.
Повний текст джерелаJones, D. P., and 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, no. 2 (March 7, 2000): 146–51. http://dx.doi.org/10.1115/1.556164.
Повний текст джерелаWong, C. M., and W. K. Tso. "Seismic loading for buildings with setbacks." Canadian Journal of Civil Engineering 21, no. 5 (October 1, 1994): 863–71. http://dx.doi.org/10.1139/l94-092.
Повний текст джерелаAntariksawan, Anhar Riza, Surip Widodo, and Hendro Tjahjono. "PARAMETRIC STUDY OF LOCA IN TRIGA-2000 USING RELAP5/SCDAP CODE." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 19, no. 2 (May 26, 2017): 59. http://dx.doi.org/10.17146/tdm.2017.19.2.3279.
Повний текст джерелаUi, Atsushi, and 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, no. 2 (October 2004): 281–90. http://dx.doi.org/10.13182/nse04-a2458.
Повний текст джерелаJin, 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 (March 2020): 110443. http://dx.doi.org/10.1016/j.nucengdes.2019.110443.
Повний текст джерелаPošta, Borna, and Siniša Šadek. "Mathematical model of the NPP Krško PCFV system for the RELAP5 computer code." Journal of Energy - Energija 66, no. 1-4 (June 23, 2022): 226–40. http://dx.doi.org/10.37798/2017661-4106.
Повний текст джерелаRacca, Stefano, and 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.
Повний текст джерелаTong, Michael T., Ian Halliwell, and Louis J. Ghosn. "A Computer Code for Gas Turbine Engine Weight and Disk Life Estimation." Journal of Engineering for Gas Turbines and Power 126, no. 2 (April 1, 2004): 265–70. http://dx.doi.org/10.1115/1.1691980.
Повний текст джерелаMartin, Robert P., and 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.
Повний текст джерелаEbiwonjumi, Bamidele, Peng Zhang, and 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.
Повний текст джерелаZhou, Lin, Qingsheng Zhao, Shukai Chi, Yanlong Li, Lanjun Liu, and 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, no. 1 (January 2019): 155014771982600. http://dx.doi.org/10.1177/1550147719826001.
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