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Results 1 to 25 of 493

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On the Evaluation of Discrepant Scientific Data with Unrecognized ErrorsCACUCI, Dan G; IONESCU-BUJOR, Mihaela.Nuclear science and engineering. 2010, Vol 165, Num 1, pp 1-17, issn 0029-5639, 17 p.Article

A Monte Carlo Approach to Nuclear Model Parameter Uncertainties PropagationDE SAINT JEAN, Cyrille; NOGUERE, Gilles; HABERT, Benoit et al.Nuclear science and engineering. 2009, Vol 161, Num 3, pp 363-370, issn 0029-5639, 8 p.Article

A parallel algorithm with interface prediction and correction for spherical geometric transport equationZHENYING HONG; GUANGWEI YUAN.Progress in nuclear energy (New series). 2009, Vol 51, Num 2, pp 268-273, issn 0149-1970, 6 p.Article

Absolute Total np and pp Cross-Section DeterminationsARNDT, R. A; BRISCOE, W. J; LAPTEV, A. B et al.Nuclear science and engineering. 2009, Vol 162, Num 3, pp 312-318, issn 0029-5639, 7 p.Article

Extensive Set of Cross-Section Covariance Estimates in the Fast Neutron RegionPIGNI, M. T; HERMAN, M; OBLOZINSKY, P et al.Nuclear science and engineering. 2009, Vol 162, Num 1, pp 25-40, issn 0029-5639, 16 p.Article

A Wavelet-Based Finite Element Method for the Self-Shielding Issue in Neutron TransportLE TELLIER, R; FOURNIER, D; RUGGIERI, J. M et al.Nuclear science and engineering. 2009, Vol 163, Num 1, pp 34-55, issn 0029-5639, 22 p.Article

Measurement of 67Zn(n,p)67Cu, 92Mo(n,p)92mNb, and 98Mo(n,γ)99Mo Reaction Cross Sections at Incident Neutron Energies of En = 1 .6 and 3.7 MeVBHIKE, Megha; SAXENA, A; ROY, B. J et al.Nuclear science and engineering. 2009, Vol 163, Num 2, pp 175-182, issn 0029-5639, 8 p.Article

The Systemic Behavior of the Binding Energy of Heavy IsotopesRONEN, Yigal.Nuclear science and engineering. 2009, Vol 163, Num 1, pp 91-97, issn 0029-5639, 7 p.Article

Surface and Volume Integrals of Uncollided Adjoint Fluxes and Forward-Adjoint Flux ProductsFAVORITE, Jeffrey A; BLEDSOE, Keith C; KETCHESON, David I et al.Nuclear science and engineering. 2009, Vol 163, Num 1, pp 73-84, issn 0029-5639, 12 p.Article

DELAYED-GAMMA SIMULATION USING MCNPXDURKEE, Joe W; MCKINNEY, Gregg W; TRELLUE, Holly R et al.Nuclear technology. 2009, Vol 168, Num 3, pp 761-764, issn 0029-5450, 4 p.Conference Paper

ENDF70: A CONTINUOUS-ENERGY MCNP NEUTRON DATA LIBRARY BASED ON ENDF/B-VII.0TRELLUE, Holly R; LITTLE, Robert C; WHITE, Morgan C et al.Nuclear technology. 2009, Vol 168, Num 3, pp 832-836, issn 0029-5450, 5 p.Conference Paper

ON COMPUTING NEUTRON TRANSMISSION FROM THE RESPONSES OF A VOID FRACTION EVALUATION SCHEME WITH MIXED BEAMSDE ABREU, Marcos P.Nuclear technology. 2009, Vol 168, Num 2, pp 369-372, issn 0029-5450, 4 p.Conference Paper

RECENT DEVELOPMENTS TO THE MONTE CARLO CODE MCBENDCOWAN, P; DOBSON, G; WRIGHT, G. A et al.Nuclear technology. 2009, Vol 168, Num 3, pp 780-784, issn 0029-5450, 5 p.Conference Paper

RESULTS OF THE NONELASTIC REACTION CODE BRIEFF FOR NUCLEAR DATADUARTE, H.Nuclear technology. 2009, Vol 168, Num 3, pp 596-600, issn 0029-5450, 5 p.Conference Paper

SIMULTANEOUS OPTIMIZATION OF TALLIES IN DIFFICULT SHIELDING PROBLEMSPEPLOW, Douglas E; EVANS, Thomas M; WAGNER, John C et al.Nuclear technology. 2009, Vol 168, Num 3, pp 785-792, issn 0029-5450, 8 p.Conference Paper

Anisotropy and Particle Conservation for Trajectory-Based Deterministic MethodsLE TELLIER, R; HEBERT, A.Nuclear science and engineering. 2008, Vol 158, Num 1, pp 28-39, issn 0029-5639, 12 p.Article

Study of the effect of anisotropic scattering on the critical slab problem in neutron transport theory using Chebyshev polynomialsOZTÜRK, H.Kerntechnik (1987). 2008, Vol 73, Num 5-6, pp 284-287, issn 0932-3902, 4 p.Article

Analytical solution for two-group diffusion equations in a multilayered slab using Laplace Transform TechniqueLEMOS, R. S. M; VILHENA, M. T; SILVA, F. C et al.Progress in nuclear energy (New series). 2008, Vol 50, Num 7, pp 747-756, issn 0149-1970, 10 p.Conference Paper

Fourier convergence analysis of two-dimensional/one-dimensional coupling methods for the three-dimensional neutron diffusion eigenvalue problemsHYUN CHUL LEE; JAE MAN NOH; HYUNG KOOK JOO et al.Nuclear science and engineering. 2007, Vol 156, Num 1, pp 74-85, issn 0029-5639, 12 p.Article

Measurements of the 152Sm(γ,n) cross section with laser-compton scatering γ rays and the photon difference methodHARA, Kaoru Y; HARADA, Hideo; KITATANI, Fumito et al.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 7, pp 938-945, issn 0022-3131, 8 p.Article

Simple Estimation of Fission Yields with Selective Channel Scission ModelOHTA, Masayuki; NAKAMURA, Shoji.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 12, pp 1491-1499, issn 0022-3131, 9 p.Article

Physique des réacteurs: Traitement des données nucléaires = Reactor physics: Nuclear data processingDIOP, Cheikh M'backé.Techniques de l'ingénieur. Génie nucléaire. 2007, Vol BN1, Num BN3012, issn 1762-875X, BN3012.1-BN3012.21Article

A quasilinear implicit Riemann solver for the time-dependent Pn equationsMCCLARREN, Ryan G; HOLLOWAY, James Paul; BRUNNER, Thomas A et al.Nuclear science and engineering. 2007, Vol 155, Num 2, pp 290-299, issn 0029-5639, 10 p.Conference Paper

The boundary source method with arbitrary order anisotropic scatteringVAN DEN EYNDE, Gert; BEAUWENS, Robert; MUND, Ernest et al.Nuclear science and engineering. 2007, Vol 155, Num 2, pp 300-309, issn 0029-5639, 10 p.Conference Paper

Analytic function expansion nodal (AFEN) method in hexagonal-Z three-dimensional geometry for neutron diffusion calculationCHO, Nam Zin; LEE, Jaejun.Journal of Nuclear Science and Technology. 2006, Vol 43, Num 11, pp 1320-1326, issn 0022-3131, 7 p.Article

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