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Volume 151

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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