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L1 convergence of the discrete ordinates for the neutron transport equation in an infinite cyclindrical domainASADZADEH, M.Nuclear science and engineering. 1992, Vol 112, Num 4, pp 383-391, issn 0029-5639Article

Alternative forms of the time-dependent neutron transport equationCOPPA, G. G. M; DULLA, S; PEANO, F et al.Progress in nuclear energy (New series). 2008, Vol 50, Num 8, pp 934-938, issn 0149-1970, 5 p.Article

Displacement damage quantification in future fusion systemsO'BRIEN, M. H; LOUGHLIN, M. J.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 2536-2542, issn 0920-3796, 7 p.Conference Paper

Analysis of communication costs for domain decomposed Monte Carlo methods in nuclear reactor analysisSIEGEL, A; SMITH, K; FISCHER, P et al.Journal of computational physics (Print). 2012, Vol 231, Num 8, pp 3119-3125, issn 0021-9991, 7 p.Article

Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problemBÜLBÜL, A; ANLI, F.Kerntechnik (1987). 2008, Vol 73, Num 4, pp 163-166, issn 0932-3902, 4 p.Article

Diffusion limit for the linear Boltzmann equation of the neutron transport theoryBANASIAK J; MIKA, J. R.Mathematical methods in the applied sciences. 1994, Vol 17, Num 13, pp 1071-1087, issn 0170-4214Article

Neutron transport modelsMAKAI, M.Progress in nuclear energy (New series). 1996, Vol 30, Num 3, pp 321-331, issn 0149-1970Article

On the importance of effective convergence velocity of synthetic acceleration methods in neutron transportCOPPA, G. G. M; RAVETTO, P; COLOMBO, V et al.Progress in nuclear energy (New series). 1996, Vol 30, Num 3, pp 265-276, issn 0149-1970Article

A stationary criticality problem in general Lp-space for energy dependent neutron transport in cylindrical geometryBORGIOLI, G; FROSALI, G.Zeitschrift für angewandte Mathematik und Physik. 1984, Vol 35, Num 2, pp 166-180, issn 0044-2275Article

Simultaneous Monte Carlo zero-variance estimates of several correlated meansBOOTH, T. E.Nuclear science and engineering. 1998, Vol 129, Num 2, pp 199-202, issn 0029-5639Article

Foundations of finite element applications to neutron transportACKROYD, R. T.Progress in nuclear energy (New series). 1995, Vol 29, Num 1, pp 43-56, issn 0149-1970Article

Variational derivation of multigroup P2 equations and boundary conditions in planar geometryRULKO, R. P.Nuclear science and engineering. 1995, Vol 121, Num 3, pp 371-392, issn 0029-5639Article

Diffusion theory with discontinuitiesPOMRANING, G. C; RULKO, R; BINGJING SU et al.Nuclear science and engineering. 1994, Vol 118, Num 1, pp 1-23, issn 0029-5639Article

Tibere : une méthode de calcul de l'effet de l'hétérogénéïté d'un réseau sur les fuites de neutrons = Tibere : a calculational method of the effect of lattice heterogeneity on the neutron leakageBenoist, Pierre; Petrovic, Ivan.1992, 69 p.Report

Monte Carlo estimates of transport solutions to the isotropic slab problemBOOTH, T. E.Nuclear science and engineering. 1998, Vol 130, Num 3, pp 374-385, issn 0029-5639Article

Variational P1 approximations of general-geometry multigroup transport problemsRULKO, R. P; TOMASEVIC, D; LARSEN, E. W et al.Nuclear science and engineering. 1995, Vol 121, Num 3, pp 393-404, issn 0029-5639Article

An improved neutron transport algorithm for HZETRNSLABA, T. C; BLATTNIG, S. R; CLOWDSLEY, M. S et al.Advances in space research. 2010, Vol 46, Num 6, pp 800-810, issn 0273-1177, 11 p.Article

Neutron and photon transport in Fe with the employment of TENDL 2009, CENDL 3.1, JENDL 4 and JENDL 4 evolution from JENDL 3.3 in case of FeKOST'AL, Michal; CVACHOVEC, František; CVACHOVEC, Jiří et al.Nuclear engineering and design. 2012, Vol 249, pp 275-286, issn 0029-5493, 12 p.Article

Determination of mean squared slowing-down distance for Am-Be neutrons in water using BF3-detectorMIRZA, N. M; MIRZA, S. M; IQBAL, M et al.Radiation physics and chemistry (1993). 1996, Vol 48, Num 4, pp 413-417, issn 0969-806XArticle

Some new results pertaining to criticality and time eigenvalues of one-speed neutron transport equationSAHNI, D. C.Progress in nuclear energy (New series). 1996, Vol 30, Num 3, pp 305-320, issn 0149-1970Article

Biases in Monte Carlo eigenvalue calculationsGELBARD, E. M; GU, A. G.Nuclear science and engineering. 1994, Vol 117, Num 1, pp 1-9, issn 0029-5639Article

Une approche non déterministe de la neutronique modélisation = A non-determinist approach to neutronic modelingVerwaerde, D.1993, 29 p.Report

Spherical albedo problem for isotropic scatteringTÜRECI, R. G.Kerntechnik (1987). 2008, Vol 73, Num 4, pp 167-170, issn 0932-3902, 4 p.Article

A simple derivation of the neutron transport equationPAZSIT, I.Nuclear science and engineering. 1992, Vol 112, Num 4, pp 369-374, issn 0029-5639Article

Narrow-duct-streaming calculations using generalized configuration factors within the discrete ordinates methodBROCKMANN, H.Nuclear science and engineering. 1999, Vol 132, Num 1, pp 127-134, issn 0029-5639Article

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