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Calculating the Second Eigenpair in Criticality Calculations Using the Monte Carlo Method with Source Points Pairing as an Efficient Net-Weight (Cancellation) AlgorithmBO SHI; PETROVIC, Bojan.Nuclear science and engineering. 2012, Vol 172, Num 2, pp 138-150, issn 0029-5639, 13 p.Article
Development of a HEX-Z Partially Homogenized Benchmark Model for the FFTF Isothermal Physics MeasurementsBESS, John D.Nuclear science and engineering. 2012, Vol 171, Num 1, pp 32-40, issn 0029-5639, 9 p.Article
Evaluations of Fission Chain Yields for 239Pu from Fission-Spectrum NeutronsTHOMPSON, I. J; DARDENNE, Y. M. X. M; KENNEALLY, J. M et al.Nuclear science and engineering. 2012, Vol 171, Num 2, pp 85-135, issn 0029-5639, 51 p.Article
Fission Neutron Spectrum Sensitivity Study for the Case of Advanced Heavy Water ReactorKUMAR, Anek; GANESAN, S.Nuclear science and engineering. 2012, Vol 172, Num 1, pp 20-32, issn 0029-5639, 13 p.Article
Generation of Few-Group Diffusion Theory Constants by Monte Carlo Code McCARDHO JIN PARK; HYUNG JIN SHIM; HAN GYU JOO et al.Nuclear science and engineering. 2012, Vol 172, Num 1, pp 66-77, issn 0029-5639, 12 p.Article
Heuristic Methods for Assigning Spent Nuclear Fuel Assemblies to Canisters for Final DisposalRANTA, Timo; CAMERON, Frank.Nuclear science and engineering. 2012, Vol 171, Num 1, pp 41-51, issn 0029-5639, 11 p.Article
Neutron Interactions with 3He Revisited—I: Elastic Scattering Around and Beyond 10 MeVDROSG, M; AVALOS ORTIZ, R; LISOWSKI, P. W et al.Nuclear science and engineering. 2012, Vol 172, Num 1, pp 87-101, issn 0029-5639, 15 p.Article
New Approach to Space-Dependent Kinetic Analysis by the Integral Kinetic ModelTAKEZAWA, Hiroki; OBARA, Toru.Nuclear science and engineering. 2012, Vol 171, Num 1, pp 1-12, issn 0029-5639, 12 p.Article
Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi AccidentREMPE, Joy; FARMER, Mitchell; CORRADINI, Michael et al.Nuclear science and engineering. 2012, Vol 172, Num 3, pp 223-248, issn 0029-5639, 26 p.Article
Uncertainty Quantification for New Approaches to Spent Fuel AssayBURR, Tom; CONLIN, Jeremy; JIANWEI HU et al.Nuclear science and engineering. 2012, Vol 172, Num 2, pp 180-192, issn 0029-5639, 13 p.Article
A Monte Carlo Lattice Code with Probability Tables and Optimized Energy MeshesMARTIN, Nicolas; HEBERT, Alain.Nuclear science and engineering. 2011, Vol 167, Num 3, pp 177-195, issn 0029-5639, 19 p.Article
Calculation of the (a, n) Emission from Plutonium Nitrate and Plutonium Uranyl Nitrate SolutionsSWINHOE, M. T.Nuclear science and engineering. 2011, Vol 167, Num 2, pp 171-175, issn 0029-5639, 5 p.Article
Feynman-Alpha and Rossi-Alpha Formulas with Delayed Neutrons for Subcritical Reactors Driven by Pulsed Non-Poisson Sources with Correlation Between Different PulsesRANA, Y. S; DEGWEKER, S. B.Nuclear science and engineering. 2011, Vol 169, Num 1, pp 98-109, issn 0029-5639, 12 p.Article
Perspectives on Advanced Simulation for Nuclear Reactor Safety ApplicationsKELLY, J; CORRADINI, M; BUDNITZ, R et al.Nuclear science and engineering. 2011, Vol 168, Num 2, pp 128-137, issn 0029-5639, 10 p.Article
Scalable Parallel Prefix Solvers for Discrete Ordinates Transport in MultidimensionsPAUTZ, Shawn D; PANDYA, Tara M; ADAMS, Marvin L et al.Nuclear science and engineering. 2011, Vol 169, Num 3, pp 245-261, issn 0029-5639, 17 p.Article
Uncertainty Propagation in Monte Carlo Depletion AnalysisHO JIN PARK; HYUNG JIN SHIM; CHANG HYO KIM et al.Nuclear science and engineering. 2011, Vol 167, Num 3, pp 196-208, issn 0029-5639, 13 p.Article
A Discrete Generalized Multigroup Energy Expansion TheoryLEI ZHU; FORGET, Benoit.Nuclear science and engineering. 2010, Vol 166, Num 3, pp 239-253, issn 0029-5639, 15 p.Article
A Transport Acceleration Scheme for Multigroup Discrete Ordinates with UpscatteringEVANS, Thomas M; CLARNO, Kevin T; MOREL, Jim E et al.Nuclear science and engineering. 2010, Vol 165, Num 3, pp 292-304, issn 0029-5639, 13 p.Article
Asymptotic Diffusion-Limit Accuracy of Sn Angular Differencing SchemesBAILEY, Teresa S; MOREL, Jim E; CHANG, Jae H et al.Nuclear science and engineering. 2010, Vol 165, Num 2, pp 149-169, issn 0029-5639, 21 p.Article
Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation—I: Mathematical FrameworkCACUCI, Dan G; IONESCU-BUJOR, Mihaela.Nuclear science and engineering. 2010, Vol 165, Num 1, pp 18-44, issn 0029-5639, 27 p.Article
Calculation of the Integral Kinetic Model Transient Parameters by the Monte Carlo Method for Space-Dependent Kinetic AnalysisTAKEZAWA, Hiroki; OBARA, Toru.Nuclear science and engineering. 2010, Vol 164, Num 1, pp 80-86, issn 0029-5639, 7 p.Article
Comments on Monte Carlo Probability of Initiation Estimates for Neutron Fission ChainsBOOTH, Thomas E.Nuclear science and engineering. 2010, Vol 166, Num 2, pp 175-178, issn 0029-5639, 4 p.Article
Double-Differential Cross Sections of the Particle Emission in Neutron-Induced Reactions on 209BiYINLU HAN; PING LIU; CHONGHAI CAI et al.Nuclear science and engineering. 2010, Vol 164, Num 2, pp 185-203, issn 0029-5639, 19 p.Article
Extension of Differential Operator Method to Inhomogeneous Problems with Internal and External Neutron SourcesFEDOROVICH RASKACH, Kirill.Nuclear science and engineering. 2010, Vol 165, Num 3, pp 320-330, issn 0029-5639, 11 p.Article
Fourier Convergence Analysis of the Rebalance Methods for Discrete Ordinates Transport Equations in Eigenvalue ProblemsSER GI HONG; KIM, Kang-Seog; JAE SEUNG SONG et al.Nuclear science and engineering. 2010, Vol 164, Num 1, pp 33-52, issn 0029-5639, 20 p.Article