Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 155
Table of Contents
Nuclear Science and Engineering / Volume 155 / Number 1
January 2007
Nuclear Science and Engineering / Volume 155 / Number 2
February 2007
Nuclear Science and Engineering / Volume 155 / Number 3
March 2007
Preface
Richard Sanchez
Nuclear Science and Engineering / Volume 155 / Number 2 / Page vii
A New Approximation for the Neutron Albedo
Ronald C. Brockhoff, J. Kenneth Shultis
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 1-17
Format:electronic copy (download)
Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses
Mark L. Williams
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 18-36
Multigroup Adjoint Transport Solution Using the Method of Cyclic Characteristics
M. Assawaroongruengchot, G. Marleau
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 37-52
Plutonium Denaturing by 238Pu
G. Kessler
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 53-73
Neutron Scattering from an Asymmetric Rotor: 197Au
Alan B. Smith
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 74-83
Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes
P. Talou, T. Kawano, P. G. Young, M. B. Chadwick, R. E. MacFarlane
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 84-95
Radial and Azimuthal 235U Fission and 238U Capture Distributions in BWR UO2 Pins: CASMO-4 and MCNP4C Versus Activation Foil Measurements
K. Macku, F. Jatuff, M. Murphy, M. Plaschy, P. Grimm, O. P. Joneja, R. Chawla
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 96-101
Studies on Effective Atomic Numbers and Electron Densities in Some Commonly Used Solvents
Ashok Kumar, Sukhpal Singh, Gurmel S. Mudahar, Kulwant Singh Thind
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 102-108
Polynomial Chaos Functions and Neutron Diffusion
M. M. R. Williams
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 109-118
A New Approach to Spatio-Temporal Calculation of Nuclear Reactor Cores Using Neural Computing
Mehrdad Boroushaki, Mohammad B. Ghofrani, Caro Lucas
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 119-130
Monte Carlo Modeling of Delayed Neutrons from Photofission
Enrico Padovani, Maura Monville, Sara A. Pozzi
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 131-142
CEARCPG: A Monte Carlo Simulation Code for Normal and Coincidence Prompt-Gamma-Ray Neutron Activation Analysis
Xiaogang Han, Robin P. Gardner, W. A. Metwally
Nuclear Science and Engineering / Volume 155 / Number 1 / Pages 143-153
A Hybrid Monte Carlo-Deterministic Method for Global Particle Transport Calculations
Troy L. Becker, Allan B. Wollaber, Edward W. Larsen
Nuclear Science and Engineering / Volume 155 / Number 2 / Pages 155-167
A Lumped Linear-Discontinuous Spatial Discretization Scheme for Triangular-Mesh Sn Calculations in r-z Geometry
Jim E. Morel, Alejandro Gonzalez-Aller, James S. Warsa
Nuclear Science and Engineering / Volume 155 / Number 2 / Pages 168-178
An Efficient Exponential Directional Iterative Differencing Scheme for Three-Dimensional Sn Computations in XYZ Geometry
Glenn E. Sjoden
Nuclear Science and Engineering / Volume 155 / Number 2 / Pages 179-189
A Two-Dimensional Discontinuous Heterogeneous Finite Element Method for Neutron Transport Calculations
Emiliano Masiello, Richard Sanchez
Nuclear Science and Engineering / Volume 155 / Number 2 / Pages 190-207
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