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Volume 159

Number 1

A Hybrid Transport-Diffusion Algorithm for Monte Carlo Radiation-Transport Simulations on Adaptive-Refinement Meshes in XY Geometry

Jeffery D. Densmore, Thomas M. Evans, Michael W. Buksas

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 1-22

Technical Paper

Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods

R. J. Sheu, A. Y. Chen, Y.-W. H. Liu, S. H. Jiang

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 23-36

Technical Paper

Efficient Generation of One-Group Cross Sections for Coupled Monte Carlo Depletion Calculations

E. Fridman, E. Shwageraus, A. Galperin

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 37-47

Technical Paper / dx.doi.org/10.13182/NSE07-34

Use of Local Variation Method for Nuclear Design Calculations

A. I. Zhukov

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 48-55

Technical Paper

New 237Np Burning Strategy in a Supercritical CO2-Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss

Hoai Nam Tran, Yasuyoshi Kato

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 83-93

Technical Paper

Subthreshold Fission Cross Section of 237Np

F. Tovesson, T. S. Hill

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 94-101

Technical Paper / dx.doi.org/10.13182/NSE07-55

Spallation Product Distributions and Neutron Multiplicities for Accelerator-Driven System Using the CRISP Code

S. Anéfalos Pereira, A. Deppman, G. Silva, J. R. Maiorino, A. dos Santos, S. B. Duarte, O. A. P. Tavares, F. Garcia

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 102-105

Technical Note

 
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