Journal articles on the topic '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.
Full textVosoughi, 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.
Full textTÜRECİ, 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.
Full textTsyfra, 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.
Full textSengupta, 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.
Full textKadem, 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.
Full textBourhrara, 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.
Full textOzturk, 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.
Full textMancusi, 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.
Full textChen, 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.
Full textKhromov, 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.
Full textWilliams, 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.
Full textSaracco, 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.
Full textYíldíz, 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.
Full textWang, 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.
Full textZhao, 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.
Full textChiba, 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.
Full textLiemert, 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.
Full textProlo 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.
Full textZheng, 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.
Full textRodriguez, 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.
Full textKim, 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.
Full textSeleznev, 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.
Full textGuo, 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.
Full textLiu, 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.
Full textAnli, 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.
Full textZemskov, 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.
Full textCalloo, 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.
Full textMerk, 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.
Full textGupta, 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.
Full textWillert, 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.
Full textBoffi, 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.
Full textŻurkowski, 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.
Full textSobolev, 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.
Full textNelson, 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.
Full textBernal, 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.
Full textGonçalves, 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.
Full textWillert, 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.
Full textHongchun, 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.
Full textNguyen, 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.
Full textAtalay, 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.
Full textShulaia, 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.
Full textSanchez, 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.
Full textGüleçyüz, 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.
Full textDouglass, 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.
Full textLogoteta, Domenico. "Hyperons in Neutron Stars." Universe 7, no. 11 (October 28, 2021): 408. http://dx.doi.org/10.3390/universe7110408.
Full textJohnson, 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.
Full textKadem, 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.
Full textBülbül, 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.
Full textYildiz, 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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