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Volume 159

Number 1

Table of Contents

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 / dx.doi.org/10.13182/NSE159-01

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 / dx.doi.org/10.13182/NSE159-23

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 / dx.doi.org/10.13182/NSE159-48

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

G. Kessler

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 56-82

Technical Paper / dx.doi.org/10.13182/NSE159-56

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 / dx.doi.org/10.13182/NSE159-83

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 / dx.doi.org/10.13182/NSE159-102

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