Artículos de revistas sobre el tema "Neutron transport problem"
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Jarmouni-Idrissi, K. y L. Thevenot. "HOMOGENIZATION OF A NONLINEAR NEUTRON TRANSPORT PROBLEM". Transport Theory and Statistical Physics 31, n.º 2 (21 de mayo de 2002): 93–123. http://dx.doi.org/10.1081/tt-120003969.
Texto completoVosoughi, Naser, Akbar Salehi, Majid Shahriari y Enzo Tonti. "Direct discrete method and its application to neutron transport problems". Nuclear Technology and Radiation Protection 18, n.º 2 (2003): 12–23. http://dx.doi.org/10.2298/ntrp0302012v.
Texto completoTÜRECİ, R. Gökhan. "Machine Learning Applications to the One-speed Neutron Transport Problems". Cumhuriyet Science Journal 43, n.º 4 (27 de diciembre de 2022): 726–38. http://dx.doi.org/10.17776/csj.1163514.
Texto completoTsyfra, Ivan y Tomasz Czyżycki. "Symmetry and Solution of Neutron Transport Equations in Nonhomogeneous Media". Abstract and Applied Analysis 2014 (2014): 1–9. http://dx.doi.org/10.1155/2014/724238.
Texto completoSengupta, A. "Full range solution of half space neutron transport problem". ZAMP Zeitschrift f�r angewandte Mathematik und Physik 46, n.º 1 (enero de 1995): 40–60. http://dx.doi.org/10.1007/bf00952255.
Texto completoKadem, Abdelouahab. "Analytical solutions for the neutron transport using the spectral methods". International Journal of Mathematics and Mathematical Sciences 2006 (2006): 1–11. http://dx.doi.org/10.1155/ijmms/2006/16214.
Texto completoBourhrara, Lahbib y Richard Sanchez. "Existence Result for the Kinetic Neutron Transport Problem in the Presence of Delayed Neutrons". Transport Theory and Statistical Physics 35, n.º 3-4 (agosto de 2006): 137–56. http://dx.doi.org/10.1080/00411450600901748.
Texto completoOzturk, Hakan. "The influence of linear anisotropic scattering of one-speed neutrons on the critical size of a slab with reflective boundary conditions". Nuclear Technology and Radiation Protection 32, n.º 3 (2017): 236–41. http://dx.doi.org/10.2298/ntrp1703236o.
Texto completoMancusi, Davide y Andrea Zoia. "TOWARDS ZERO-VARIANCE SCHEMES FOR KINETIC MONTE-CARLO SIMULATIONS". EPJ Web of Conferences 247 (2021): 04010. http://dx.doi.org/10.1051/epjconf/202124704010.
Texto completoChen, Gen-Shun y Anthony W. Leung. "Positive Solutions for Reactor Multigroup Neutron Transport Systems: Criticality Problem". SIAM Journal on Applied Mathematics 49, n.º 3 (junio de 1989): 871–87. http://dx.doi.org/10.1137/0149051.
Texto completoKhromov, V., E. Kryuchkov, G. Tikhomirov, L. Goncharov y V. Kondakov. "Probabilistic Method of Discrete Ordinates in a Neutron Transport Problem". Nuclear Science and Engineering 121, n.º 2 (octubre de 1995): 264–76. http://dx.doi.org/10.13182/nse95-a28563.
Texto completoWilliams, M. M. R. "The flat flux problem in one-speed neutron transport theory". Annals of Nuclear Energy 30, n.º 5 (marzo de 2003): 513–47. http://dx.doi.org/10.1016/s0306-4549(02)00108-1.
Texto completoSaracco, P., N. Abrate, M. Burrone, S. Dulla y P. Ravetto. "STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION". EPJ Web of Conferences 247 (2021): 03018. http://dx.doi.org/10.1051/epjconf/202124703018.
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 completoWang, Xinyu, Bin Zhang, Yixue Chen y Jun Xiong. "Verification of the Discrete Ordinates Goal-Oriented Multi-Collision Source Algorithm with Neutron Streaming Problems". Energies 15, n.º 22 (8 de noviembre de 2022): 8335. http://dx.doi.org/10.3390/en15228335.
Texto completoZhao, 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 completoChiba, Go y Kazuyuki Numata. "Neutron transport benchmark problem proposal for fast critical assembly without homogenizations". Annals of Nuclear Energy 34, n.º 6 (junio de 2007): 443–48. http://dx.doi.org/10.1016/j.anucene.2007.02.018.
Texto completoLiemert, André y Alwin Kienle. "The line source problem in anisotropic neutron transport with internal reflection". Annals of Nuclear Energy 60 (octubre de 2013): 206–9. http://dx.doi.org/10.1016/j.anucene.2013.05.007.
Texto completoProlo Filho, João Francisco y Marco Paulsen Rodrigues. "A Closed Form Solution for a One-Dimensional Multi-Layered Neutron Transport Problem by Analytical Discrete Ordinates Method". Defect and Diffusion Forum 372 (marzo de 2017): 50–59. http://dx.doi.org/10.4028/www.scientific.net/ddf.372.50.
Texto completoZheng, Weixiong y Ryan G. McClarren. "Accurate least-squares P scaling based on problem optical thickness for solving neutron transport problems". Progress in Nuclear Energy 101 (noviembre de 2017): 394–400. http://dx.doi.org/10.1016/j.pnucene.2017.06.001.
Texto completoRodriguez, Damian Martin, Shane J. Kennedy y Phillip M. Bentley. "Properties of elliptical guides for neutron beam transport and applications for new instrumentation concepts". Journal of Applied Crystallography 44, n.º 4 (28 de junio de 2011): 727–37. http://dx.doi.org/10.1107/s0021889811018590.
Texto completoKim, Inhyung y Yonghee Kim. "INVESTIGATION ON DETERMINISTIC TRUNCATION TO CONTINUOUS ENERGY MONTE CARLO NEUTRON TRANSPORT CALCULATION". EPJ Web of Conferences 247 (2021): 04023. http://dx.doi.org/10.1051/epjconf/202124704023.
Texto completoSeleznev, E., V. Bereznev, I. Chernova y A. Belov. "USING PARTIAL EQUATIONS FOR ANALYSIS OF THE FAST BREEDER REACTOR KINETICS". PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, n.º 3 (26 de septiembre de 2019): 153–62. http://dx.doi.org/10.55176/2414-1038-2019-3-153-162.
Texto completoGuo, Yan y Lei Wu. "Regularity of Milne problem with geometric correction in 3D". Mathematical Models and Methods in Applied Sciences 27, n.º 03 (marzo de 2017): 453–524. http://dx.doi.org/10.1142/s0218202517500075.
Texto completoLiu, Yang, Hangyu Shi, Liangzhi Cao, Qi Zheng y Xiaoping Ouyang. "A new method to solve the neutron transport problem of spherical structure". Annals of Nuclear Energy 165 (enero de 2022): 108749. http://dx.doi.org/10.1016/j.anucene.2021.108749.
Texto completoAnli, Fikret, Faruk Yaşa, Süleyman Güngör y Hakan Öztürk. "TN approximation to neutron transport equation and application to critical slab problem". Journal of Quantitative Spectroscopy and Radiative Transfer 101, n.º 1 (septiembre de 2006): 129–34. http://dx.doi.org/10.1016/j.jqsrt.2005.11.010.
Texto completoZemskov, E., K. Melnikov y I. Tormyshev. "CALCULATION OF THE PARAMETERS OF STOCHASTIC NEUTRON KINETICS IN ZERO POWER NUCLEAR REACTORS". PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, n.º 1 (26 de marzo de 2019): 250–62. http://dx.doi.org/10.55176/2414-1038-2019-1-250-262.
Texto completoCalloo, Ansar, Romain Le Tellier y David Couyras. "COMPARISON OF CHEBYSHEV AND ANDERSON ACCELERATIONS FOR THE NEUTRON TRANSPORT EQUATION". EPJ Web of Conferences 247 (2021): 03001. http://dx.doi.org/10.1051/epjconf/202124703001.
Texto completoMerk, B. "An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production". Nuclear Science and Engineering 161, n.º 1 (enero de 2009): 49–67. http://dx.doi.org/10.13182/nse161-49.
Texto completoGupta, Anurag y R. S. Modak. "Krylov sub-space methods for K-eigenvalue problem in 3-D neutron transport". Annals of Nuclear Energy 31, n.º 18 (diciembre de 2004): 2113–25. http://dx.doi.org/10.1016/j.anucene.2004.07.001.
Texto completoWillert, Jeffrey, H. Park y D. A. Knoll. "A comparison of acceleration methods for solving the neutron transport k -eigenvalue problem". Journal of Computational Physics 274 (octubre de 2014): 681–94. http://dx.doi.org/10.1016/j.jcp.2014.06.044.
Texto completoBoffi, V. C., W. L. Dunn y G. Spiga. "A Rigorous Solution to the Classical Space-Dependent Neutron Slowing Down Transport Problem". Nuclear Science and Engineering 99, n.º 3 (julio de 1988): 197–207. http://dx.doi.org/10.13182/nse88-a28993.
Texto completoŻurkowski, Wojciech, Piotr Sawicki, Wojciech Kubiński y Piotr Darnowski. "Application of genetic algorithms in optimization of SFR nuclear reactor design". Nukleonika 66, n.º 4 (25 de noviembre de 2021): 139–45. http://dx.doi.org/10.2478/nuka-2021-0021.
Texto completoSobolev, Artem V. y Pavel A. Danilov. "Problems of radiation safety calculations related to spent nuclear fuel transport casks". Nuclear Energy and Technology 6, n.º 1 (27 de marzo de 2020): 43–47. http://dx.doi.org/10.3897/nucet.6.51778.
Texto completoNelson, Adam G., William Boyd y Paul K. Romano. "The Effect of the Flux Separability Approximation on Multigroup Neutron Transport". Journal of Nuclear Engineering 2, n.º 1 (22 de marzo de 2021): 86–96. http://dx.doi.org/10.3390/jne2010009.
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 completoGonçalves, G. A., M. T. de Vilhena y B. E. J. Bodmann. "Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering". Kerntechnik 75, n.º 1-2 (marzo de 2010): 50–52. http://dx.doi.org/10.3139/124.110051.
Texto completoWillert, Jeffrey, H. Park y William Taitano. "Applying Nonlinear Diffusion Acceleration to the Neutron Transport k-Eigenvalue Problem with Anisotropic Scattering". Nuclear Science and Engineering 181, n.º 3 (noviembre de 2015): 351–60. http://dx.doi.org/10.13182/nse14-131.
Texto completoHongchun, Wu, Liu Pingping, Zhou Yongqiang y Cao Liangzhi. "Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem". Nuclear Engineering and Design 237, n.º 1 (enero de 2007): 28–37. http://dx.doi.org/10.1016/j.nucengdes.2006.04.031.
Texto completoNguyen, Tat Nghia, Yeon Sang Jung, Thomas Downar y Changho Lee. "Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC". Annals of Nuclear Energy 129 (julio de 2019): 199–206. http://dx.doi.org/10.1016/j.anucene.2019.01.005.
Texto completoAtalay, M. A. "The critical slab problem for reflecting boundary conditions in one-speed neutron transport theory". Annals of Nuclear Energy 23, n.º 3 (febrero de 1996): 183–93. http://dx.doi.org/10.1016/0306-4549(95)00024-7.
Texto completoShulaia, D. A. y E. I. Gugushvili. "Inverse problem of spectral analysis of linear multigroup neutron transport theory in plane geometry". Transport Theory and Statistical Physics 29, n.º 6 (octubre de 2000): 711–21. http://dx.doi.org/10.1080/00411450008214531.
Texto completoSanchez, Richard y Lahbib Bourhrara. "Existence Result for the Kinetic Neutron Transport Problem with a General Albedo Boundary Condition". Transport Theory and Statistical Physics 40, n.º 2 (septiembre de 2011): 69–84. http://dx.doi.org/10.1080/00411450.2011.596607.
Texto completoGüleçyüz, M. Ç. y C. Tezcan. "The FN method for anisotropic scattering in neutron transport theory: The critical slab problem". Journal of Quantitative Spectroscopy and Radiative Transfer 56, n.º 2 (agosto de 1996): 309–13. http://dx.doi.org/10.1016/0022-4073(96)00057-x.
Texto completoDouglass, Steven y Nathan Gibson. "K-MEANS CLUSTERING OF NEUTRON SPECTRA FOR CROSS SECTION COLLAPSE". EPJ Web of Conferences 247 (2021): 03010. http://dx.doi.org/10.1051/epjconf/202124703010.
Texto completoLogoteta, Domenico. "Hyperons in Neutron Stars". Universe 7, n.º 11 (28 de octubre de 2021): 408. http://dx.doi.org/10.3390/universe7110408.
Texto completoJohnson, Andrew y Dan Kotlyar. "APPLICATION OF A CUSTOM DEPLETION FRAMEWORK TO THE PREDICTION OF NEUTRON FLUX DISTRIBUTION THROUGH DEPLETION". EPJ Web of Conferences 247 (2021): 02004. http://dx.doi.org/10.1051/epjconf/202124702004.
Texto completoKadem, Abdelouahab y Adem Kilicman. "Note on the Solution of Transport Equation by Tau Method and Walsh Functions". Abstract and Applied Analysis 2010 (2010): 1–13. http://dx.doi.org/10.1155/2010/704168.
Texto completoBülbül, A. y F. Anlı. "Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem". Kerntechnik 73, n.º 4 (septiembre de 2008): 163–66. http://dx.doi.org/10.3139/124.100559.
Texto completoYildiz, C. "The spherical harmonics method for anisotropic scattering in neutron transport theory: the critical sphere problem". Journal of Quantitative Spectroscopy and Radiative Transfer 71, n.º 1 (octubre de 2001): 25–37. http://dx.doi.org/10.1016/s0022-4073(01)00009-7.
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