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Статті в журналах з теми "Numerical Methods for Neutron Transport"
Zhao, Zhengang, and Yunying Zheng. "Numerical Approximation for Fractional Neutron Transport Equation." Journal of Mathematics 2021 (March 13, 2021): 1–14. http://dx.doi.org/10.1155/2021/6676640.
Повний текст джерелаAixiang, Huang, and Ma Yichen. "The application of modern numerical methods to the neutron transport equation." Transport Theory and Statistical Physics 26, no. 1-2 (January 1997): 65–83. http://dx.doi.org/10.1080/00411459708221775.
Повний текст джерелаShafii, Mohamad Ali. "Solution methods of neutron transport equation in nuclear reactors." Jurnal ILMU DASAR 14, no. 2 (December 4, 2013): 59. http://dx.doi.org/10.19184/jid.v14i2.320.
Повний текст джерелаYíldíz, C. "Calculation of the higher order eigenvalues for a homogeneous sphere using the FN method." Kerntechnik 66, no. 1-2 (January 1, 2001): 33–36. http://dx.doi.org/10.1515/kern-2001-0008.
Повний текст джерелаCarta, M., S. Dulla, V. Peluso, P. Ravetto, and 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.
Повний текст джерелаItoh, Naoki. "Transport Processes in Dense Stellar Plasmas." International Astronomical Union Colloquium 147 (1994): 394–419. http://dx.doi.org/10.1017/s0252921100026464.
Повний текст джерелаBurke, Paul E., Kyle E. Remley, and 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.
Повний текст джерелаBernal, Álvaro, Rafael Miró, Damián Ginestar, and 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.
Повний текст джерелаMimoun, Jordan G., Carlos Torres-Verdín, and William E. Preeg. "Quantitative interpretation of pulsed neutron capture logs: Part 1 — Fast numerical simulation." GEOPHYSICS 76, no. 3 (May 2011): E81—E93. http://dx.doi.org/10.1190/1.3569600.
Повний текст джерелаVarma, Vishnu, Bernhard Müller, and 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, no. 4 (October 19, 2021): 6033–48. http://dx.doi.org/10.1093/mnras/stab2983.
Повний текст джерелаДисертації з теми "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.
Повний текст джерелаBARBARINO, ANDREA. "Numerical Methods for Neutron Transport Calculations of Nuclear Reactors." Doctoral thesis, Politecnico di Torino, 2014. http://hdl.handle.net/11583/2561774.
Повний текст джерелаMarquez, Damian Jose Ignacio. "Multilevel acceleration of neutron transport calculations." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2007. http://hdl.handle.net/1853/19731.
Повний текст джерелаCommittee 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.
Повний текст джерелаCommittee 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.
Повний текст джерелаBlake, 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.
Повний текст джерелаABRATE, NICOLO'. "Methods for safety and stability analysis of nuclear systems." Doctoral thesis, Politecnico di Torino, 2022. http://hdl.handle.net/11583/2971611.
Повний текст джерелаDi, 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.
Знайти повний текст джерелаSheehan, 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.
Повний текст джерелаMuddle, John Christopher. "Advanced numerical methods for neutron star interfaces." Thesis, University of Southampton, 2015. https://eprints.soton.ac.uk/375551/.
Повний текст джерелаКниги з теми "Numerical Methods for Neutron Transport"
Lewis, E. E. Computational methods of neutron transport. La Grange Park, Ill., USA: American Nuclear Society, 1993.
Знайти повний текст джерелаIvanovich, Lebedev Vi͡a︡cheslav, ed. Numerical methods in the theory of neutron transport. 2nd ed. Chur, Switzerland: Harwood, 1986.
Знайти повний текст джерелаComputational methods for two-phase flow and particle transport. Singapore: World Scientific Publishing Co., 2013.
Знайти повний текст джерелаLászló, Koblinger, ed. Monte Carlo particle transport methods: Neutron and photon calculations. Boca Raton: CRC Press, 1991.
Знайти повний текст джерела1941-, Greenberg W., and Polewczak J. 1952-, eds. Modern mathematical methods in transport theory. Basel: Birkhäuser Verlag, 1991.
Знайти повний текст джерелаA, Silebi C., ed. Computational transport phenomena: Numerical methods for the solution of transport problems. Cambridge, U.K: Cambridge University Press, 1997.
Знайти повний текст джерелаGupta, Anurag. Krylov sub-space methods for K-eigenvalue problem in 3-D multigroup neutron transport. Mumbai: Bhabha Atomic Research Centre, 2004.
Знайти повний текст джерелаFrank, Graziani, ed. Computational methods in transport: Verification and validation. Berlin: Springer, 2008.
Знайти повний текст джерелаCenter, 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.
Знайти повний текст джерелаAckroyd, Ron T. Finite element methods for particle transport: Applications to reactor and radiation physics. Taunton, Somerset, England: Research Studies Press, 1997.
Знайти повний текст джерелаЧастини книг з теми "Numerical Methods for Neutron Transport"
Marguet, Serge. "Computational Neutron Transport Methods." In The Physics of Nuclear Reactors, 593–727. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-59560-3_9.
Повний текст джерелаLewis, E. E. "Second-Order Neutron Transport Methods." In Nuclear Computational Science, 85–115. Dordrecht: Springer Netherlands, 2009. http://dx.doi.org/10.1007/978-90-481-3411-3_2.
Повний текст джерелаPoirier, D. R., and G. H. Geiger. "Numerical Methods and Models." In Transport Phenomena in Materials Processing, 571–610. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-48090-9_16.
Повний текст джерелаZohuri, Bahman. "Numerical Methods in Modeling Neutron Diffusion." In 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.
Повний текст джерелаZohuri, Bahman. "Numerical Methods in Modeling Neutron Diffusion." In 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.
Повний текст джерелаDurran, Dale R. "Beyond One-Dimensional Transport." In 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.
Повний текст джерелаKersch, Alfred, and William J. Morokoff. "Numerical Methods for Rarefied Gas Dynamics." In Transport Simulation in Microelectronics, 77–99. Basel: Birkhäuser Basel, 1995. http://dx.doi.org/10.1007/978-3-0348-9080-9_3.
Повний текст джерелаDautray, Robert, and Jacques-Louis Lions. "Transport." In 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.
Повний текст джерелаPoirier, E. J., and D. R. Poirier. "Numerical Methods and Models." In 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.
Повний текст джерелаYeh, Gourt-Tsyh. "Numerical Methods for Advection-Dominant Transport." In Computational Subsurface Hydrology, 93–198. Boston, MA: Springer US, 2000. http://dx.doi.org/10.1007/978-1-4615-4371-8_3.
Повний текст джерелаТези доповідей конференцій з теми "Numerical Methods for Neutron Transport"
Wu, Hongchun, Guoming Liu, Liangzhi Cao, and Qichang Chen. "Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29442.
Повний текст джерелаZhang, J. "A coupled thermo-mechanical and neutron diffusion numerical model for irradiated concrete." In AIMETA 2022. Materials Research Forum LLC, 2023. http://dx.doi.org/10.21741/9781644902431-4.
Повний текст джерелаPanta Pazos, Rube´n, and Marco Tu´llio de Vilhena. "Variational Approach in Transport Theory." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49233.
Повний текст джерелаGanapol, Barry D. "A 1D Monoenergetic Neutron Transport Benchmark in an Infinite Medium." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30156.
Повний текст джерелаKoreshi, Zafar Ullah, and Sadaf Siddiq. "Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29971.
Повний текст джерелаSun, Qizheng, Tengfei Zhang, Xiaojing Liu, Xiang Chai, and Jinbiao Xiong. "A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91525.
Повний текст джерелаJevremovic, Tatjana, Mathieu Hursin, Nader Satvat, John Hopkins, Shanjie Xiao, and Godfree Gert. "Performance, Accuracy and Efficiency Evaluation of a Three-Dimensional Whole-Core Neutron Transport Code AGENT." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89561.
Повний текст джерелаPanta Pazos, Ruben, Marco Tullio de Vilhena, and Eliete Biasotto Hauser. "Solution and Study of the Two-Dimensional Nodal Neutron Transport Equation." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22611.
Повний текст джерелаLiu, Guoming, and Hongchun Wu. "Transmission Probability Method Based on Triangular-Z Mesh for Solving Neutron Transport Equation in Three-Dimensional Geometry." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48607.
Повний текст джерелаLiang, Liang, Hongchun Wu, Liangzhi Cao, and Youqi Zheng. "Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15725.
Повний текст джерелаЗвіти організацій з теми "Numerical Methods for Neutron Transport"
Brown, P. N. Novel Parallel Numerical Methods for Radiation& Neutron Transport. Office of Scientific and Technical Information (OSTI), March 2001. http://dx.doi.org/10.2172/15005562.
Повний текст джерелаNicholas Tsoulfanidis and Elmer Lewis. Neutron Transport Methods for Accelerator-Driven Systems. Office of Scientific and Technical Information (OSTI), February 2005. http://dx.doi.org/10.2172/836901.
Повний текст джерелаCai, Wei. Multi-scale and Multi-physics Numerical Methods for Modeling Transport in Mesoscopic Systems. Fort Belvoir, VA: Defense Technical Information Center, September 2012. http://dx.doi.org/10.21236/ada572398.
Повний текст джерелаCai, Wei. Multi-scale and Multi-physics Numerical Methods for Modeling Transport in Mesoscopic Systems. Fort Belvoir, VA: Defense Technical Information Center, October 2014. http://dx.doi.org/10.21236/ada617374.
Повний текст джерелаTaylor, G., C. Dong, and 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), March 2010. http://dx.doi.org/10.2172/974328.
Повний текст джерелаChang, B. Analytical Tests for Ray Effect Errors in Discrete Ordinate Methods for Solving the Neutron Transport Equation. Office of Scientific and Technical Information (OSTI), March 2004. http://dx.doi.org/10.2172/15014046.
Повний текст джерелаWharry, Janelle, and 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), December 2018. http://dx.doi.org/10.2172/1493700.
Повний текст джерелаWang, Dean, Thomas Downar, Yunlin Xu, Yulong Xing, and 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), April 2019. http://dx.doi.org/10.2172/1511575.
Повний текст джерелаGill, 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), May 2007. http://dx.doi.org/10.2172/903208.
Повний текст джерелаSagar, B., and 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), March 1990. http://dx.doi.org/10.2172/137710.
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