cc.\*:("001B20H20G")
Résultats 1 à 25 sur 164
Sélection :
Convergence analysis of additive angular dependent rebalance acceleration for the discrete ordinates transport calculationsCHANG JE PARK; NAM ZIN CHO.Nuclear science and engineering. 2002, Vol 142, Num 1, pp 64-74, issn 0029-5639, 11 p.Article
Parallelization of MCNP Monte Carlo neutron and photon transport code in parallel virtual machine and message passing interfaceDENG, L; XIE, Z.-S.Journal of Nuclear Science and Technology. 1999, Vol 36, Num 7, pp 626-629, issn 0022-3131Article
Influence of anisotropic scattering on the size of time-dependent systems in monoenergetic neutron transportYILDIZ, C.Journal of physics. D, Applied physics (Print). 1999, Vol 32, Num 3, pp 317-325, issn 0022-3727Article
Calcul Parallèle pour les Equations de Diffusion et de Transport Homogènes en Neutronique = Parallel Computing for Homogeneous Diffusion and Transport Equations in NeutronicsPinchedez, Katia; Jaffré, Jérôme.1999, 348 p.Thesis
CONTRIBUTION A LA RESOLUTION DE L'EQUATION DE BOLTZMANN EN MULTIGROUPE PAR LES METHODES DETERMINISTES ET MONTE CARLO = CONTRIBUTIONS TO THE SOLUTION OF THE MULTIGROUP BOLTZMANN EQUATION BY DETERMINIST AND MONTE CARLO METHODSMao, Li; Sanchez, Richard.1998, 219 p.Thesis
Advances in the development of a subgroup method for the self-shielding of resonant isotopes in arbitrary geometriesHEBERT, A.Nuclear science and engineering. 1997, Vol 126, Num 3, pp 245-263, issn 0029-5639Article
Modélisation des fuites hétérogènes de neutrons dans un réacteur nucléaire = Modelling of Heterogenous Neutron Leakages in a Nuclear ReactorWohleber, Xavier; Mathonnière, Gilles.1997, 178 p.Thesis
A quasi-isotropic reflecting boundary condition for the TIBERE heterogeneous leakage modelPETROVIC, I; BENOIST, P; MARLEAU, G et al.Nuclear science and engineering. 1996, Vol 122, Num 2, pp 151-166, issn 0029-5639Article
Analytical numerical methods applied to linear discontinuous angular approximations of the transport equation in slab geometryDE BARROS, R. C; CARDONA, A. V; DE VILHENA, M. T et al.Kerntechnik (1987). 1996, Vol 61, Num 2-3, pp 111-116, issn 0932-3902Article
The simplified P2 approximationTOMASEVIC, D. I; LARSEN, E. W.Nuclear science and engineering. 1996, Vol 122, Num 3, pp 309-325, issn 0029-5639Article
A hybrid multigroup/continuous-energy Monte Carlo method for solving the Boltzmann-Fokker-Planck equationMOREL, J. E; LORENCE, L. J; KENSEK, R. P et al.Nuclear science and engineering. 1996, Vol 124, Num 3, pp 369-389, issn 0029-5639Article
A modified P3-like approximation to the transport equationSU, B; POMRANING, G. C.Nuclear science and engineering. 1996, Vol 124, Num 2, pp 309-319, issn 0029-5639Article
Wavelet theory for solution of the neutron diffusion equationNAM ZIN CHO; CHANG JE PARK.Nuclear science and engineering. 1996, Vol 124, Num 3, pp 417-430, issn 0029-5639Article
Collision probability calculation and multigroup flux solvers using PVMQADDOURI, A; ROY, R; MAYRAND, M et al.Nuclear science and engineering. 1996, Vol 123, Num 3, pp 392-402, issn 0029-5639Article
A diffusion-synthetic acceleration technique for the even-parity Sn equations with anisotropic scatteringMOREL, J. E; MCGHEE, J. M.Nuclear science and engineering. 1995, Vol 120, Num 3, pp 147-164, issn 0029-5639Article
Development of Monte Carlo machine for particle transport problemHIGUCHI, K; ASAI, K; AKIMOTO, M et al.Journal of Nuclear Science and Technology. 1995, Vol 32, Num 10, pp 953-964, issn 0022-3131Article
A fission-source acceleration technique for time-dependent even-parity Sn calculationsMOREL, J. E; MCGHEE, J. M.Nuclear science and engineering. 1994, Vol 116, Num 2, pp 73-85, issn 0029-5639Article
14 MeV neutron distribution in a shield with a hollow channelBELOUSOV, S. I; ANTONOV, S. Y; ILIEVA, K. D et al.Nuclear engineering and design. 1994, Vol 150, Num 1, pp 177-181, issn 0029-5493Article
Optimization of a double bent-crystal diffractometer for neutron small-angle scattering experimentsSAROUN, J; LUKAS, P; MIKULA, P et al.Journal of applied crystallography. 1994, Vol 27, pp 80-88, issn 0021-8898, 1Article
Temporal accuracy of the nonequilibrium radiation diffusion equations applied to two-dimensional multimaterial simulationsMOUSSEAU, Vincent A; KNOLL, Dana A.Nuclear science and engineering. 2006, Vol 154, Num 2, pp 174-189, issn 0029-5639, 16 p.Article
Charge diffusion constant in hot and dense hadronic matter: A hadro-molecular-dynamics calculationSASAKI, N; MIYAMURA, O; MUROYA, S et al.Europhysics letters (Print). 2001, Vol 54, Num 1, pp 38-44, issn 0295-5075Article
From Fourier transforms to singular eigenfunctions for multigroup transportGANAPOL, B. D.Nuclear science and engineering. 2001, Vol 137, Num 3, pp 400-410, issn 0029-5639Article
Réduction de variance pour l'intégration numérique et pour le calcul critique en transport neutronique = Variance reduction for numerical integration and criticality in neutron transport theoryMaire, Sylvain; Talay, Denis.2001, 168 p.Thesis
Résolution d'un spectromètre de diffusion de neutrons aux petits angles = Resolution of neutrons diffusion spectrometer on small anglesLAIREZ, D.Journal de physique. IV. 1999, Vol 9, Num 1, pp Pr1.67-Pr1.81, issn 1155-4339Conference Paper
Solution of the neutron transport equation by the collision probability method in three dimensional domainsOUJIDI, B; SANCHEZ, R; ERRADI, L et al.Radiation physics and chemistry (1993). 1998, Vol 51, Num 4-6, pp 409-410, issn 0969-806XConference Paper