Number 1 | Number 2 | Number 3
Zero-Variance Monte Carlo Schemes Revisited
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 1-22
Technical Paper
A Linear Surface Characteristics Approximation for Neutron Transport in Unstructured Meshes
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 23-40
Technical Paper
Generalized Energy Condensation Theory
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 41-58
Technical Paper
Optimization of One-Pass Transuranic Deep Burn in a Modular Helium Reactor
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 59-74
Technical Paper
Corrosion of Materials by Liquid NaK Coolant in a Nuclear Power System
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 75-97
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 98-107
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 108-122
Technical Paper
Measurement of Differential Cross Section for the 64Zn(n,
)61Ni Reaction at 2.54, 4.00, and 5.50 MeV
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 123-128
Technical Paper
Verification and Determination of the Decay Heat in Spent PWR Fuel by Means of Gamma Scanning
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 129-143
Technical Note
The Systematic Behavior of the Spontaneous Fission Branching Ratios of Even-Z Isotopes
Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 144-147
Technical Note
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 149-167
Technical Paper
Evaluation of Neutron Cross Sections for a Complete Set of Nd Isotopes
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 168-189
Technical Paper
Reevaluation of Prompt Neutron Emission Multiplicity Distributions for Spontaneous Fission
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 190-199
Technical Paper
Measurement of the 236U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV up to 25 keV
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 200-206
Technical Paper
An Attempt to Improve Empirical Formulas for (n,p) and (n,
) Cross Sections
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 207-216
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 217-231
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 232-241
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 242-252
Technical Paper
Resonance Absorption in Materials with Randomly Dispersed Grains
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 253-260
Technical Paper
Scattering Reduction of the Double-Heterogeneity Treatment in Dragon
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 261-266
Technical Note
A Quantitative Theory of Angular Truncation Errors in Three-Dimensional SN Calculations
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 267-283
Technical Paper
Moments-Based Versions of the Spherical Geometry Method of Tubes in Thick, Diffusive Regions
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 284-301
Technical Paper
Decay Ratio Estimation of BWR Signals Based on Wavelet Ridges
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 302-317
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 318-333
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 334-348
Technical Paper
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 349-362
Technical Paper
Measurement of the Photonuclear (
,n) Reaction Cross Section for 129I Using Bremsstrahlung Photons
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 363-369
Technical Paper
Sensitivity of Photoneutron Production to Perturbations in Cross-Section Data
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 370-377
Technical Paper
Preparation and Characterization of Pu0.5Am0.5O2-x-MgO Ceramic/Ceramic Composites
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 378-384
Technical Paper
A Continuous Finite Element-Based, Discontinuous Finite Element Method for SN Transport
Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 385-400
Technical Note