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ANS > Publications > Journals > Nuclear Science and Engineering > Volume 159
Number 1  ·  Number 2
Number 1 · May 2008
Table of Contents
A Hybrid Transport-Diffusion Algorithm for Monte Carlo Radiation-Transport Simulations on Adaptive-Refinement Meshes in XY Geometry
Volume 159 · Number 1 · May 2008 · Pages 1-22
Technical Paper

Jeffery D. Densmore, Thomas M. Evans, Michael W. Buksas
Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods
Volume 159 · Number 1 · May 2008 · Pages 23-36
Technical Paper

R. J. Sheu, A. Y. Chen, Y.-W. H. Liu, S. H. Jiang
Efficient Generation of One-Group Cross Sections for Coupled Monte Carlo Depletion Calculations
Volume 159 · Number 1 · May 2008 · Pages 37-47
Technical Paper

E. Fridman, E. Shwageraus, A. Galperin
Use of Local Variation Method for Nuclear Design Calculations
Volume 159 · Number 1 · May 2008 · Pages 48-55
Technical Paper

A. I. Zhukov
Proliferation Resistance of Americium Originating from Spent Irradiated Reactor Fuel of Pressurized Water Reactors, Fast Reactors, and Accelerator-Driven Systems with Different Fuel Cycle Options
Volume 159 · Number 1 · May 2008 · Pages 56-82
Technical Paper

G. Kessler
New 237Np Burning Strategy in a Supercritical CO2-Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss
Volume 159 · Number 1 · May 2008 · Pages 83-93
Technical Paper

Hoai Nam Tran, Yasuyoshi Kato
Subthreshold Fission Cross Section of 237Np
Volume 159 · Number 1 · May 2008 · Pages 94-101
Technical Paper

F. Tovesson, T. S. Hill
Spallation Product Distributions and Neutron Multiplicities for Accelerator-Driven System Using the CRISP Code
Volume 159 · Number 1 · May 2008 · Pages 102-105
Technical Note

S. Anéfalos Pereira, A. Deppman, G. Silva, J. R. Maiorino, A. dos Santos, S. B. Duarte, O. A. P. Tavares, F. Garcia
Number 2 · June 2008
Table of Contents
A Functional Monte Carlo Method for k-Eigenvalue Problems
Volume 159 · Number 2 · June 2008 · Pages 107-126
Technical Paper

Edward W. Larsen, Jinan Yang
Linear and Quadratic Hexahedral Wavelets on the Sphere for Angular Discretizations of the Boltzmann Transport Equation
Volume 159 · Number 2 · June 2008 · Pages 127-152
Technical Paper

A. G. Buchan, C. C. Pain, M. D. Eaton, A. J. H. Goddard, R. P. Smedley-Stevenson
Benchmark Calculation of WIMS/RFSP Against Physics Measurement Data of Wolsong Nuclear Power Plants
Volume 159 · Number 2 · June 2008 · Pages 153-168
Technical Paper

Hangbok Choi, Chang Je Park
A Neutron Transport Benchmark in One-Dimensional Cylindrical Geometry: Revisited
Volume 159 · Number 2 · June 2008 · Pages 169-181
Technical Paper

B. D. Ganapol
Measurements of Thermal Neutron Diffraction and Inelastic Scattering in Reactor-Grade Graphite
Volume 159 · Number 2 · June 2008 · Pages 182-198
Technical Paper

C. D. Bowman, D. C. Bowman, T. Hill, J. Long, A. P. Tonchev, W. Tornow, F. Trouw, Sven Vogel, R. L. Walter, S. Wender, V. Yuan
Measurement of Neutron Capture Resonance Integrals on Bromine Isotopes
Volume 159 · Number 2 · June 2008 · Pages 199-212
Technical Paper

E. L. Dorval, M. A. Arribére, S. Ribeiro Guevara
Modeling of High-Precision Neutron Nonelastic Cross Sections
Volume 159 · Number 2 · June 2008 · Pages 213-220
Technical Paper

F. S. Dietrich, J. D. Anderson, R. W. Bauer, S. M. Grimes, D. P. McNabb
Identification of Optimal Number of Histogram Bars for Large Data Trends
Volume 159 · Number 2 · June 2008 · Pages 221-227
Technical Note

Plamen V. Petkov
Proliferation Resistance of Americium Originating from Spent Irradiated Reactor Fuel of Pressurized Water Reactors, Fast Reactors, and Accelerator-Driven Systems with Different Fuel Cycle Options
Volume 159 · Number 2 · June 2008 · Pages 228-228
Corrigendum

G. Kessler
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