Статті в журналах з теми "Neutron transport problem"
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Jarmouni-Idrissi, K., and L. Thevenot. "HOMOGENIZATION OF A NONLINEAR NEUTRON TRANSPORT PROBLEM." Transport Theory and Statistical Physics 31, no. 2 (May 21, 2002): 93–123. http://dx.doi.org/10.1081/tt-120003969.
Повний текст джерелаVosoughi, Naser, Akbar Salehi, Majid Shahriari, and Enzo Tonti. "Direct discrete method and its application to neutron transport problems." Nuclear Technology and Radiation Protection 18, no. 2 (2003): 12–23. http://dx.doi.org/10.2298/ntrp0302012v.
Повний текст джерелаTÜRECİ, R. Gökhan. "Machine Learning Applications to the One-speed Neutron Transport Problems." Cumhuriyet Science Journal 43, no. 4 (December 27, 2022): 726–38. http://dx.doi.org/10.17776/csj.1163514.
Повний текст джерелаTsyfra, Ivan, and 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.
Повний текст джерелаSengupta, A. "Full range solution of half space neutron transport problem." ZAMP Zeitschrift f�r angewandte Mathematik und Physik 46, no. 1 (January 1995): 40–60. http://dx.doi.org/10.1007/bf00952255.
Повний текст джерелаKadem, 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.
Повний текст джерелаBourhrara, Lahbib, and Richard Sanchez. "Existence Result for the Kinetic Neutron Transport Problem in the Presence of Delayed Neutrons." Transport Theory and Statistical Physics 35, no. 3-4 (August 2006): 137–56. http://dx.doi.org/10.1080/00411450600901748.
Повний текст джерелаOzturk, 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, no. 3 (2017): 236–41. http://dx.doi.org/10.2298/ntrp1703236o.
Повний текст джерелаMancusi, Davide, and 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.
Повний текст джерелаChen, Gen-Shun, and Anthony W. Leung. "Positive Solutions for Reactor Multigroup Neutron Transport Systems: Criticality Problem." SIAM Journal on Applied Mathematics 49, no. 3 (June 1989): 871–87. http://dx.doi.org/10.1137/0149051.
Повний текст джерелаKhromov, V., E. Kryuchkov, G. Tikhomirov, L. Goncharov, and V. Kondakov. "Probabilistic Method of Discrete Ordinates in a Neutron Transport Problem." Nuclear Science and Engineering 121, no. 2 (October 1995): 264–76. http://dx.doi.org/10.13182/nse95-a28563.
Повний текст джерелаWilliams, M. M. R. "The flat flux problem in one-speed neutron transport theory." Annals of Nuclear Energy 30, no. 5 (March 2003): 513–47. http://dx.doi.org/10.1016/s0306-4549(02)00108-1.
Повний текст джерелаSaracco, P., N. Abrate, M. Burrone, S. Dulla, and 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.
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 джерелаWang, Xinyu, Bin Zhang, Yixue Chen, and Jun Xiong. "Verification of the Discrete Ordinates Goal-Oriented Multi-Collision Source Algorithm with Neutron Streaming Problems." Energies 15, no. 22 (November 8, 2022): 8335. http://dx.doi.org/10.3390/en15228335.
Повний текст джерелаZhao, 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 джерелаChiba, Go, and Kazuyuki Numata. "Neutron transport benchmark problem proposal for fast critical assembly without homogenizations." Annals of Nuclear Energy 34, no. 6 (June 2007): 443–48. http://dx.doi.org/10.1016/j.anucene.2007.02.018.
Повний текст джерелаLiemert, André, and Alwin Kienle. "The line source problem in anisotropic neutron transport with internal reflection." Annals of Nuclear Energy 60 (October 2013): 206–9. http://dx.doi.org/10.1016/j.anucene.2013.05.007.
Повний текст джерелаProlo Filho, João Francisco, and 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 (March 2017): 50–59. http://dx.doi.org/10.4028/www.scientific.net/ddf.372.50.
Повний текст джерелаZheng, Weixiong, and Ryan G. McClarren. "Accurate least-squares P scaling based on problem optical thickness for solving neutron transport problems." Progress in Nuclear Energy 101 (November 2017): 394–400. http://dx.doi.org/10.1016/j.pnucene.2017.06.001.
Повний текст джерелаRodriguez, Damian Martin, Shane J. Kennedy, and Phillip M. Bentley. "Properties of elliptical guides for neutron beam transport and applications for new instrumentation concepts." Journal of Applied Crystallography 44, no. 4 (June 28, 2011): 727–37. http://dx.doi.org/10.1107/s0021889811018590.
Повний текст джерелаKim, Inhyung, and 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.
Повний текст джерелаSeleznev, E., V. Bereznev, I. Chernova, and 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, no. 3 (September 26, 2019): 153–62. http://dx.doi.org/10.55176/2414-1038-2019-3-153-162.
Повний текст джерелаGuo, Yan, and Lei Wu. "Regularity of Milne problem with geometric correction in 3D." Mathematical Models and Methods in Applied Sciences 27, no. 03 (March 2017): 453–524. http://dx.doi.org/10.1142/s0218202517500075.
Повний текст джерелаLiu, Yang, Hangyu Shi, Liangzhi Cao, Qi Zheng, and Xiaoping Ouyang. "A new method to solve the neutron transport problem of spherical structure." Annals of Nuclear Energy 165 (January 2022): 108749. http://dx.doi.org/10.1016/j.anucene.2021.108749.
Повний текст джерелаAnli, Fikret, Faruk Yaşa, Süleyman Güngör, and Hakan Öztürk. "TN approximation to neutron transport equation and application to critical slab problem." Journal of Quantitative Spectroscopy and Radiative Transfer 101, no. 1 (September 2006): 129–34. http://dx.doi.org/10.1016/j.jqsrt.2005.11.010.
Повний текст джерелаZemskov, E., K. Melnikov, and 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, no. 1 (March 26, 2019): 250–62. http://dx.doi.org/10.55176/2414-1038-2019-1-250-262.
Повний текст джерелаCalloo, Ansar, Romain Le Tellier, and 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.
Повний текст джерелаMerk, B. "An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production." Nuclear Science and Engineering 161, no. 1 (January 2009): 49–67. http://dx.doi.org/10.13182/nse161-49.
Повний текст джерелаGupta, Anurag, and R. S. Modak. "Krylov sub-space methods for K-eigenvalue problem in 3-D neutron transport." Annals of Nuclear Energy 31, no. 18 (December 2004): 2113–25. http://dx.doi.org/10.1016/j.anucene.2004.07.001.
Повний текст джерелаWillert, Jeffrey, H. Park, and D. A. Knoll. "A comparison of acceleration methods for solving the neutron transport k -eigenvalue problem." Journal of Computational Physics 274 (October 2014): 681–94. http://dx.doi.org/10.1016/j.jcp.2014.06.044.
Повний текст джерелаBoffi, V. C., W. L. Dunn, and G. Spiga. "A Rigorous Solution to the Classical Space-Dependent Neutron Slowing Down Transport Problem." Nuclear Science and Engineering 99, no. 3 (July 1988): 197–207. http://dx.doi.org/10.13182/nse88-a28993.
Повний текст джерелаŻurkowski, Wojciech, Piotr Sawicki, Wojciech Kubiński, and Piotr Darnowski. "Application of genetic algorithms in optimization of SFR nuclear reactor design." Nukleonika 66, no. 4 (November 25, 2021): 139–45. http://dx.doi.org/10.2478/nuka-2021-0021.
Повний текст джерелаSobolev, Artem V., and Pavel A. Danilov. "Problems of radiation safety calculations related to spent nuclear fuel transport casks." Nuclear Energy and Technology 6, no. 1 (March 27, 2020): 43–47. http://dx.doi.org/10.3897/nucet.6.51778.
Повний текст джерелаNelson, Adam G., William Boyd, and Paul K. Romano. "The Effect of the Flux Separability Approximation on Multigroup Neutron Transport." Journal of Nuclear Engineering 2, no. 1 (March 22, 2021): 86–96. http://dx.doi.org/10.3390/jne2010009.
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 джерелаGonçalves, G. A., M. T. de Vilhena, and B. E. J. Bodmann. "Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering." Kerntechnik 75, no. 1-2 (March 2010): 50–52. http://dx.doi.org/10.3139/124.110051.
Повний текст джерелаWillert, Jeffrey, H. Park, and William Taitano. "Applying Nonlinear Diffusion Acceleration to the Neutron Transport k-Eigenvalue Problem with Anisotropic Scattering." Nuclear Science and Engineering 181, no. 3 (November 2015): 351–60. http://dx.doi.org/10.13182/nse14-131.
Повний текст джерелаHongchun, Wu, Liu Pingping, Zhou Yongqiang, and Cao Liangzhi. "Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem." Nuclear Engineering and Design 237, no. 1 (January 2007): 28–37. http://dx.doi.org/10.1016/j.nucengdes.2006.04.031.
Повний текст джерелаNguyen, Tat Nghia, Yeon Sang Jung, Thomas Downar, and Changho Lee. "Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC." Annals of Nuclear Energy 129 (July 2019): 199–206. http://dx.doi.org/10.1016/j.anucene.2019.01.005.
Повний текст джерелаAtalay, M. A. "The critical slab problem for reflecting boundary conditions in one-speed neutron transport theory." Annals of Nuclear Energy 23, no. 3 (February 1996): 183–93. http://dx.doi.org/10.1016/0306-4549(95)00024-7.
Повний текст джерелаShulaia, D. A., and E. I. Gugushvili. "Inverse problem of spectral analysis of linear multigroup neutron transport theory in plane geometry." Transport Theory and Statistical Physics 29, no. 6 (October 2000): 711–21. http://dx.doi.org/10.1080/00411450008214531.
Повний текст джерелаSanchez, Richard, and Lahbib Bourhrara. "Existence Result for the Kinetic Neutron Transport Problem with a General Albedo Boundary Condition." Transport Theory and Statistical Physics 40, no. 2 (September 2011): 69–84. http://dx.doi.org/10.1080/00411450.2011.596607.
Повний текст джерелаGüleçyüz, M. Ç., and C. Tezcan. "The FN method for anisotropic scattering in neutron transport theory: The critical slab problem." Journal of Quantitative Spectroscopy and Radiative Transfer 56, no. 2 (August 1996): 309–13. http://dx.doi.org/10.1016/0022-4073(96)00057-x.
Повний текст джерелаDouglass, Steven, and 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.
Повний текст джерелаLogoteta, Domenico. "Hyperons in Neutron Stars." Universe 7, no. 11 (October 28, 2021): 408. http://dx.doi.org/10.3390/universe7110408.
Повний текст джерелаJohnson, Andrew, and 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.
Повний текст джерелаKadem, Abdelouahab, and 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.
Повний текст джерелаBülbül, A., and F. Anlı. "Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem." Kerntechnik 73, no. 4 (September 2008): 163–66. http://dx.doi.org/10.3139/124.100559.
Повний текст джерелаYildiz, C. "The spherical harmonics method for anisotropic scattering in neutron transport theory: the critical sphere problem." Journal of Quantitative Spectroscopy and Radiative Transfer 71, no. 1 (October 2001): 25–37. http://dx.doi.org/10.1016/s0022-4073(01)00009-7.
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