Literatura académica sobre el tema "Numerical Methods for Neutron Transport"
Crea una cita precisa en los estilos APA, MLA, Chicago, Harvard y otros
Consulte las listas temáticas de artículos, libros, tesis, actas de conferencias y otras fuentes académicas sobre el tema "Numerical Methods for Neutron Transport".
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.
Artículos de revistas sobre el tema "Numerical Methods for Neutron Transport"
Zhao, Zhengang y Yunying Zheng. "Numerical Approximation for Fractional Neutron Transport Equation". Journal of Mathematics 2021 (13 de marzo de 2021): 1–14. http://dx.doi.org/10.1155/2021/6676640.
Texto completoAixiang, Huang y Ma Yichen. "The application of modern numerical methods to the neutron transport equation". Transport Theory and Statistical Physics 26, n.º 1-2 (enero de 1997): 65–83. http://dx.doi.org/10.1080/00411459708221775.
Texto completoShafii, Mohamad Ali. "Solution methods of neutron transport equation in nuclear reactors". Jurnal ILMU DASAR 14, n.º 2 (4 de diciembre de 2013): 59. http://dx.doi.org/10.19184/jid.v14i2.320.
Texto completoYíldíz, C. "Calculation of the higher order eigenvalues for a homogeneous sphere using the FN method". Kerntechnik 66, n.º 1-2 (1 de enero de 2001): 33–36. http://dx.doi.org/10.1515/kern-2001-0008.
Texto completoCarta, M., S. Dulla, V. Peluso, P. Ravetto y G. Bianchini. "Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods". Science and Technology of Nuclear Installations 2011 (2011): 1–8. http://dx.doi.org/10.1155/2011/584256.
Texto completoItoh, Naoki. "Transport Processes in Dense Stellar Plasmas". International Astronomical Union Colloquium 147 (1994): 394–419. http://dx.doi.org/10.1017/s0252921100026464.
Texto completoBurke, Paul E., Kyle E. Remley y David P. Griesheimer. "GPU ACCELERATION OF DOPPLER BROADENING FOR NEUTRON TRANSPORT CALCULATIONS1". EPJ Web of Conferences 247 (2021): 04017. http://dx.doi.org/10.1051/epjconf/202124704017.
Texto completoBernal, Álvaro, Rafael Miró, Damián Ginestar y Gumersindo Verdú. "Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method". Abstract and Applied Analysis 2014 (2014): 1–15. http://dx.doi.org/10.1155/2014/913043.
Texto completoMimoun, Jordan G., Carlos Torres-Verdín y William E. Preeg. "Quantitative interpretation of pulsed neutron capture logs: Part 1 — Fast numerical simulation". GEOPHYSICS 76, n.º 3 (mayo de 2011): E81—E93. http://dx.doi.org/10.1190/1.3569600.
Texto completoVarma, Vishnu, Bernhard Müller y Martin Obergaulinger. "A comparison of 2D Magnetohydrodynamic supernova simulations with the CoCoNuT-FMT and Aenus-Alcar codes". Monthly Notices of the Royal Astronomical Society 508, n.º 4 (19 de octubre de 2021): 6033–48. http://dx.doi.org/10.1093/mnras/stab2983.
Texto completoTesis sobre el tema "Numerical Methods for Neutron Transport"
ALCARO, FABIO. "Quasi-static Methods in Neutron Transport". Doctoral thesis, Politecnico di Torino, 2012. http://hdl.handle.net/11583/2501653.
Texto completoBARBARINO, ANDREA. "Numerical Methods for Neutron Transport Calculations of Nuclear Reactors". Doctoral thesis, Politecnico di Torino, 2014. http://hdl.handle.net/11583/2561774.
Texto completoMarquez, Damian Jose Ignacio. "Multilevel acceleration of neutron transport calculations". Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2007. http://hdl.handle.net/1853/19731.
Texto completoCommittee Chair: Stacey, Weston M.; Committee Co-Chair: de Oliveira, Cassiano R.E.; Committee Member: Hertel, Nolan; Committee Member: van Rooijen, Wilfred F.G.
Blackburn, Megan Satterfield. "Numerical benchmarking of a coarse-mesh transport (COMET) method for medical physics applications". Diss., Atlanta, Ga. : Georgia Institute of Technology, 2009. http://hdl.handle.net/1853/29763.
Texto completoCommittee Chair: Farzad Rahnema; Committee Co-Chair: Eric Elder; Committee Member: C.-K. Chris Wang; Committee Member: Rebecca Howell; Committee Member: Sang Cho. Part of the SMARTech Electronic Thesis and Dissertation Collection.
Byambaakhuu, Tseelmaa. "Development of Advanced Numerical Methods for Solving Neutron Transport Problems: DG-DSA and the Shishkin Mesh for Problems with Sharp Layers". The Ohio State University, 2021. http://rave.ohiolink.edu/etdc/view?acc_num=osu1618855174338701.
Texto completoBlake, Jack. "Domain decomposition methods for nuclear reactor modelling with diffusion acceleration". Thesis, University of Bath, 2016. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.698988.
Texto completoABRATE, NICOLO'. "Methods for safety and stability analysis of nuclear systems". Doctoral thesis, Politecnico di Torino, 2022. http://hdl.handle.net/11583/2971611.
Texto completoDi, Chicco Augusto. "Optimization of a calculation scheme through the parametric study of effective nuclear cross sections and application to the estimate of neutronic parameters of the ASTRID fast nuclear reactor". Master's thesis, Alma Mater Studiorum - Università di Bologna, 2018.
Buscar texto completoSheehan, B. P. "Multigrid methods for isotropic neutron transport". Connect to online resource, 2007. http://gateway.proquest.com/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:3256437.
Texto completoMuddle, John Christopher. "Advanced numerical methods for neutron star interfaces". Thesis, University of Southampton, 2015. https://eprints.soton.ac.uk/375551/.
Texto completoLibros sobre el tema "Numerical Methods for Neutron Transport"
Lewis, E. E. Computational methods of neutron transport. La Grange Park, Ill., USA: American Nuclear Society, 1993.
Buscar texto completoIvanovich, Lebedev Vi͡a︡cheslav, ed. Numerical methods in the theory of neutron transport. 2a ed. Chur, Switzerland: Harwood, 1986.
Buscar texto completoComputational methods for two-phase flow and particle transport. Singapore: World Scientific Publishing Co., 2013.
Buscar texto completoLászló, Koblinger, ed. Monte Carlo particle transport methods: Neutron and photon calculations. Boca Raton: CRC Press, 1991.
Buscar texto completo1941-, Greenberg W. y Polewczak J. 1952-, eds. Modern mathematical methods in transport theory. Basel: Birkhäuser Verlag, 1991.
Buscar texto completoA, Silebi C., ed. Computational transport phenomena: Numerical methods for the solution of transport problems. Cambridge, U.K: Cambridge University Press, 1997.
Buscar texto completoGupta, Anurag. Krylov sub-space methods for K-eigenvalue problem in 3-D multigroup neutron transport. Mumbai: Bhabha Atomic Research Centre, 2004.
Buscar texto completoFrank, Graziani, ed. Computational methods in transport: Verification and validation. Berlin: Springer, 2008.
Buscar texto completoCenter, Langley Research, ed. Development of deterministic transport methods for low energy neutrons for shielding in space. Tucson, Ariz: Engineering Experiment Station, College of Engineering and Mines, University of Arizona, 1993.
Buscar texto completoAckroyd, Ron T. Finite element methods for particle transport: Applications to reactor and radiation physics. Taunton, Somerset, England: Research Studies Press, 1997.
Buscar texto completoCapítulos de libros sobre el tema "Numerical Methods for Neutron Transport"
Marguet, Serge. "Computational Neutron Transport Methods". En The Physics of Nuclear Reactors, 593–727. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-59560-3_9.
Texto completoLewis, E. E. "Second-Order Neutron Transport Methods". En Nuclear Computational Science, 85–115. Dordrecht: Springer Netherlands, 2009. http://dx.doi.org/10.1007/978-90-481-3411-3_2.
Texto completoPoirier, D. R. y G. H. Geiger. "Numerical Methods and Models". En Transport Phenomena in Materials Processing, 571–610. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-48090-9_16.
Texto completoZohuri, Bahman. "Numerical Methods in Modeling Neutron Diffusion". En Neutronic Analysis For Nuclear Reactor Systems, 255–88. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-42964-9_5.
Texto completoZohuri, Bahman. "Numerical Methods in Modeling Neutron Diffusion". En Neutronic Analysis For Nuclear Reactor Systems, 253–83. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5_5.
Texto completoDurran, Dale R. "Beyond One-Dimensional Transport". En Numerical Methods for Fluid Dynamics, 147–201. New York, NY: Springer New York, 2010. http://dx.doi.org/10.1007/978-1-4419-6412-0_4.
Texto completoKersch, Alfred y William J. Morokoff. "Numerical Methods for Rarefied Gas Dynamics". En Transport Simulation in Microelectronics, 77–99. Basel: Birkhäuser Basel, 1995. http://dx.doi.org/10.1007/978-3-0348-9080-9_3.
Texto completoDautray, Robert y Jacques-Louis Lions. "Transport". En Mathematical Analysis and Numerical Methods for Science and Technology, 209–416. Berlin, Heidelberg: Springer Berlin Heidelberg, 2000. http://dx.doi.org/10.1007/978-3-642-58004-8_3.
Texto completoPoirier, E. J. y D. R. Poirier. "Numerical Methods and Models". En Solutions Manual To accompany Transport Phenomena in Materials Processing, 305–13. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-65130-9_16.
Texto completoYeh, Gourt-Tsyh. "Numerical Methods for Advection-Dominant Transport". En Computational Subsurface Hydrology, 93–198. Boston, MA: Springer US, 2000. http://dx.doi.org/10.1007/978-1-4615-4371-8_3.
Texto completoActas de conferencias sobre el tema "Numerical Methods for Neutron Transport"
Wu, Hongchun, Guoming Liu, Liangzhi Cao y Qichang Chen. "Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry". En 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29442.
Texto completoZhang, J. "A coupled thermo-mechanical and neutron diffusion numerical model for irradiated concrete". En AIMETA 2022. Materials Research Forum LLC, 2023. http://dx.doi.org/10.21741/9781644902431-4.
Texto completoPanta Pazos, Rube´n y Marco Tu´llio de Vilhena. "Variational Approach in Transport Theory". En 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49233.
Texto completoGanapol, Barry D. "A 1D Monoenergetic Neutron Transport Benchmark in an Infinite Medium". En 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30156.
Texto completoKoreshi, Zafar Ullah y Sadaf Siddiq. "Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion". En 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29971.
Texto completoSun, Qizheng, Tengfei Zhang, Xiaojing Liu, Xiang Chai y Jinbiao Xiong. "A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh". En 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91525.
Texto completoJevremovic, Tatjana, Mathieu Hursin, Nader Satvat, John Hopkins, Shanjie Xiao y Godfree Gert. "Performance, Accuracy and Efficiency Evaluation of a Three-Dimensional Whole-Core Neutron Transport Code AGENT". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89561.
Texto completoPanta Pazos, Ruben, Marco Tullio de Vilhena y Eliete Biasotto Hauser. "Solution and Study of the Two-Dimensional Nodal Neutron Transport Equation". En 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22611.
Texto completoLiu, Guoming y Hongchun Wu. "Transmission Probability Method Based on Triangular-Z Mesh for Solving Neutron Transport Equation in Three-Dimensional Geometry". En 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48607.
Texto completoLiang, Liang, Hongchun Wu, Liangzhi Cao y Youqi Zheng. "Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation". En 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15725.
Texto completoInformes sobre el tema "Numerical Methods for Neutron Transport"
Brown, P. N. Novel Parallel Numerical Methods for Radiation& Neutron Transport. Office of Scientific and Technical Information (OSTI), marzo de 2001. http://dx.doi.org/10.2172/15005562.
Texto completoNicholas Tsoulfanidis y Elmer Lewis. Neutron Transport Methods for Accelerator-Driven Systems. Office of Scientific and Technical Information (OSTI), febrero de 2005. http://dx.doi.org/10.2172/836901.
Texto completoCai, Wei. Multi-scale and Multi-physics Numerical Methods for Modeling Transport in Mesoscopic Systems. Fort Belvoir, VA: Defense Technical Information Center, septiembre de 2012. http://dx.doi.org/10.21236/ada572398.
Texto completoCai, Wei. Multi-scale and Multi-physics Numerical Methods for Modeling Transport in Mesoscopic Systems. Fort Belvoir, VA: Defense Technical Information Center, octubre de 2014. http://dx.doi.org/10.21236/ada617374.
Texto completoTaylor, G., C. Dong y S. Sun. NUMERICAL MODELING OF CONTAMINANT TRANSPORT IN FRACTURED POROUS MEDIA USING MIXED FINITE ELEMENT AND FINITE VOLUME METHODS. Office of Scientific and Technical Information (OSTI), marzo de 2010. http://dx.doi.org/10.2172/974328.
Texto completoChang, B. Analytical Tests for Ray Effect Errors in Discrete Ordinate Methods for Solving the Neutron Transport Equation. Office of Scientific and Technical Information (OSTI), marzo de 2004. http://dx.doi.org/10.2172/15014046.
Texto completoWharry, Janelle y Won Sik Yang. Steady-State Thermal-Hydraulic Analysis and Bowing Reactivity Evaluation Methods Based on Neutron and Gamma Transport Calculations. Office of Scientific and Technical Information (OSTI), diciembre de 2018. http://dx.doi.org/10.2172/1493700.
Texto completoWang, Dean, Thomas Downar, Yunlin Xu, Yulong Xing y Emily Shemon. Development of a Novel Accelerator for Neutron Transport Solution Using the Galerkin Spectral Element Methods (Final Report). Office of Scientific and Technical Information (OSTI), abril de 2019. http://dx.doi.org/10.2172/1511575.
Texto completoGill, Daniel Fury. Behavior of the Diamond Difference and Low-Order Nodal Numerical Transport Methods in the Thick Diffusion Limit for Slab Geometry. Office of Scientific and Technical Information (OSTI), mayo de 2007. http://dx.doi.org/10.2172/903208.
Texto completoSagar, B. y A. Runchal. PORFLO-3: A mathematical model for fluid flow, heat, and mass transport in variably saturated geologic media; Theory and numerical methods, Version 1.0. Office of Scientific and Technical Information (OSTI), marzo de 1990. http://dx.doi.org/10.2172/137710.
Texto completo