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Volume 151

Number 1 | Number 2 | Number 3

Number 1

The Ribon Extended Self-Shielding Model

Alain Hébert

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 1-24

Technical Paper

Plutonium Multirecycling in Standard PWRs Loaded with Evolutionary Fuels

Gilles Youinou, Alfredo Vasile

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 25-45

Technical Paper

Iterative Two- and One-Dimensional Methods for Three-Dimensional Neutron Diffusion Calculations

Hyun Chul Lee, Deokjung Lee, Thomas J. Downar

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 46-54

Technical Paper

Deterministic Local Sensitivity Analysis of Augmented Systems - I: Theory

Dan G. Cacuci, Mihaela Ionescu-Bujor

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 55-66

Technical Paper

Deterministic Local Sensitivity Analysis of Augmented Systems - II: Applications to the QUENCH-04 Experiment Using the RELAP5/MOD3.2 Code System

Mihaela Ionescu-Bujor, Xuezhou Jin, Dan G. Cacuci

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 67-81

Technical Paper

Development of the CRISP Package for Spallation Studies and Accelerator-Driven Systems

S. Anefalos, A. Deppman, Gilson da Silva, J. R. Maiorino, A. dos Santos, F. Garcia

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 82-87

Technical Paper

Refueling Simulation Strategy of a CANDU Reactor Based on Optimum Zone Controller Water Levels

Hangbok Choi, Do Heon Kim

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 88-94

Technical Paper

In-Phase and Out-of-Phase Oscillations in BWRs: Impact of Azimuthal Asymmetry and Second Pair of Eigenvalues

Quan Zhou, Rizwan-uddin

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 95-113

Technical Paper

Approach to Assessing the Potential Effects of Colloidal Radionuclide Transport on Nuclear Waste Repository Performance

David A. Pickett, William L. Dam

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 114-120

Technical Paper

Comparison of Oxidation Behaviors of Different Grades of Nuclear Graphite

Xiaowei Luo, Jean-Charles Robin, Suyuan Yu

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 121-127

Technical Paper

Interaction Between Hyperalkaline Fluids and Rocks Hosting Repositories for Radioactive Waste: Reactive Transport Simulations

Josep M. Soler, Urs K. Mäder

Nuclear Science and Engineering / Volume 151 / Number 1 / September 2005 / Pages 128-133

Technical Note

Number 2

Reich-Moore Parameterization of (,n) Reactions on Light Nuclei: Impact on a Neutron Source Calculation in an Oxide Fuel

Richard Babut, Olivier Bouland, Eric Fort

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 135-156

Technical Paper

An Sn Spatial Discretization Scheme for Tetrahedral Meshes

Jim E. Morel, James S. Warsa

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 157-166

Technical Paper

Spherical Harmonics Finite Element Transport Equation Solution Using a Least-Squares Approach

E. Varin, G. Samba

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 167-183

Technical Paper

Multiple Timescale Expansions for Neutron Kinetics - I: Illustrative Application to the Point-Kinetics Model

B. R. Merk, D. G. Cacuci

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 184-193

Technical Paper

Multiple Timescale Expansions for Neutron Kinetics - II: Illustrative Application to P1 and P3 Equations

B. R. Merk, D. G. Cacuci

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 194-211

Technical Paper

Temporal Adaptive Three-Grid Correction Method for Transient Nonlinear Nodal Calculations

Ku Young Chung, Chang Hyo Kim

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 212-223

Technical Paper

Insights into Stratified Splitting Techniques for Monte Carlo Neutron Transport

Thomas E. Booth

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 224-236

Technical Paper

The Inversion Point of the Isothermal Reactivity Coefficient of the IPEN/MB-01 Reactor - II: Theoretical Analysis

A. dos Santos, G. S. de Andrade e Silva, A. G. Mendonça, R. Fuga, A. Y. Abe

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 237-250

Technical Paper

Benchmark Experiments of Thermal Neutron and Capture Gamma-Ray Distributions in Concrete Using 252Cf

Yoshihiro Asano, Takeshi Sugita, Hideyuki Hirose, Takenori Suzaki

Nuclear Science and Engineering / Volume 151 / Number 2 / October 2005 / Pages 251-259

Technical Paper

Number 3

Impact of High Burnup on PWR Spent Fuel Characteristics

Zhiwen Xu, Mujid S. Kazimi, Michael J. Driscoll

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 261-273

Technical Paper

Generalized Coarse-Mesh Rebalance Method for Acceleration of Neutron Transport Calculations

Akio Yamamoto

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 274-282

Technical Paper

Information Theory and Undersampling Diagnostics for Monte Carlo Simulation of Nuclear Criticality

Taro Ueki

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 283-292

Technical Paper

Neutron Production in Semiprototypic Target Assemblies for Accelerator Transmutation Technology

G. L. Morgan, K. R. Alrick, D. W. Bowman, F. C. Cverna, N. S. P. King, P. E. Littleton, G. A. Greene, A. L. Hanson, C. L. Snead, Jr., J. M. Hall, J. Frehaut, X. Ledoux, S. Leray, E. Petibon, R. T. Thompson, P. D. Ferguson, E. A. Henry, T. E. Ward

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 293-304

Technical Paper

The Stability of 9Cr-ODS Oxide Particles Under Heavy-Ion Irradiation

T. R. Allen, J. Gan, J. I. Cole, S. Ukai, S. Shutthanandan, S. Thevuthasan

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 305-312

Technical Paper

Steam Generator Two-Phase-Flow Numerical Simulation with Liquid and Gas Momentum Equations

M. Grandotto, P. Obry

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 313-318

Technical Paper

Total and Capture Cross Sections of Dysprosium Isotopes up to 20 MeV

Y. D. Lee, S. Y. Oh, J. H. Chang

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 319-334

Technical Note

Core Subcriticality as a Tool of Safety Enhancement

Pavel M. Bokov, Danas Ridikas, Igor Slessarev, Oliver Köberl

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 335-343

Technical Note

Reactivity Effects of Streaming Between Discrete Boron Carbide Particles in Neutron Absorber Panels for Storage or Transport of Spent Nuclear Fuel

Stanley E. Turner

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 344-347

Technical Note

High-Resolution Room Temperature Spectroscopy with Lanthanum Halides

Sanjoy Mukhopadhyay

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 348-354

Technical Note

Oxidation Kinetics of Spent Low-Level Radioactive Resins

Y.-J. Huang, H. Paul Wang, Chih C. Chao, H. H. Liu, M. C. Hsiao, S. H. Liu

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 355-360

Technical Note

CEARPGA II: A Monte Carlo Simulation Code for Prompt-Gamma-Ray Neutron Activation Analysis

Wenchao Zhang, Robin P. Gardner

Nuclear Science and Engineering / Volume 151 / Number 3 / November 2005 / Pages 361-373

Computer Code Abstract

 
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