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Volume 159

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Nuclear Science and Engineering / Volume 159 / Number 1

May 2008

Table of Contents

Nuclear Science and Engineering / Volume 159 / Number 2

June 2008

Table of Contents

Nuclear Science and Engineering / Volume 159 / Number 3

July 2008

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 / Pages 1-22

May 2008

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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 / Pages 23-36

May 2008

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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 / Pages 37-47

May 2008

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Use of Local Variation Method for Nuclear Design Calculations

A. I. Zhukov

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

May 2008

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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 / Pages 83-93

May 2008

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Subthreshold Fission Cross Section of 237Np

F. Tovesson, T. S. Hill

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

May 2008

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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 / Pages 102-105

May 2008

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A Functional Monte Carlo Method for k-Eigenvalue Problems

Edward W. Larsen, Jinan Yang

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 107-126

June 2008

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Linear and Quadratic Hexahedral Wavelets on the Sphere for Angular Discretizations of the Boltzmann Transport Equation

A. G. Buchan, C. C. Pain, M. D. Eaton, A. J. H. Goddard, R. P. Smedley-Stevenson

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 127-152

June 2008

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Benchmark Calculation of WIMS/RFSP Against Physics Measurement Data of Wolsong Nuclear Power Plants

Hangbok Choi, Chang Je Park

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 153-168

June 2008

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A Neutron Transport Benchmark in One-Dimensional Cylindrical Geometry: Revisited

B. D. Ganapol

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 169-181

June 2008

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Measurements of Thermal Neutron Diffraction and Inelastic Scattering in Reactor-Grade Graphite

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

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 182-198

June 2008

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Measurement of Neutron Capture Resonance Integrals on Bromine Isotopes

E. L. Dorval, M. A. Arribére, S. Ribeiro Guevara

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 199-212

June 2008

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Modeling of High-Precision Neutron Nonelastic Cross Sections

F. S. Dietrich, J. D. Anderson, R. W. Bauer, S. M. Grimes, D. P. McNabb

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 213-220

June 2008

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Identification of Optimal Number of Histogram Bars for Large Data Trends

Plamen V. Petkov

Nuclear Science and Engineering / Volume 159 / Number 2 / Pages 221-227

June 2008

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Format:

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