ANS / Publications / Journals / Nuclear Science and Engineering

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

A Functional Monte Carlo Method for k-Eigenvalue Problems

Edward W. Larsen, Jinan Yang

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 107-126

Technical Paper / dx.doi.org/10.13182/NSE07-92

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 / June 2008 / Pages 127-152

Technical Paper / dx.doi.org/10.13182/NSE159-127

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 / June 2008 / Pages 153-168

Technical Paper / dx.doi.org/10.13182/NSE159-153

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

B. D. Ganapol

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 169-181

Technical Paper / dx.doi.org/10.13182/NSE159-169

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 / June 2008 / Pages 182-198

Technical Paper / dx.doi.org/10.13182/NSE159-182

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 / June 2008 / Pages 199-212

Technical Paper / dx.doi.org/10.13182/NSE159-199

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 / June 2008 / Pages 213-220

Technical Paper / dx.doi.org/10.13182/NSE159-213

Identification of Optimal Number of Histogram Bars for Large Data Trends

Plamen V. Petkov

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 221-227

Technical Note / dx.doi.org/10.13182/NSE159-221

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 2 / June 2008 / Page 228

Corrigendum / dx.doi.org/10.13182/NSE159-228

Analytic Function Expansion Nodal Method for Multigroup Diffusion Equations in Cylindrical (r,,z) Geometry

Nam Zin Cho, Jaejun Lee

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 229-241

Technical Paper / dx.doi.org/10.13182/NSE159-229

Finite Element Transport Using Wachspress Rational Basis Functions on Quadrilaterals in Diffusive Regions

Gregory G. Davidson, Todd S. Palmer

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 242-255

Technical Paper / dx.doi.org/10.13182/NSE159-242

Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models

Hany S. Abdel-Khalik, Paul J. Turinsky, Matthew A. Jessee

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 256-272

Technical Paper / dx.doi.org/10.13182/NSE159-256

A New Approach to Estimate Importance for Weight Window in Forward Monte Carlo Calculations

Isao Murata, Detlef Filges, Frank Goldenbaum

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 273-283

Technical Paper / dx.doi.org/10.13182/NSE159-273

Research of Point Flux Estimation Method

Chunyan Li, Junli Li, Jianping Cheng, Zhen Wu, Lucheng Pei, Jiajin Fan

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 284-295

Technical Paper / dx.doi.org/10.13182/NSE159-284

Purely Angular Effects of Photon Buildup Factors for Thin Shields of Lead, Iron, Aluminum, and Water

H. Omar Wooten, Donald J. Dudziak, Nolan E. Hertel, Drew E. Kornreich, Adam C. Davis

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 296-310

Technical Paper / dx.doi.org/10.13182/NSE06-42

The Measurement of the Coolant Pressure Fluctuation and the Mechanical Vibration of the Equipment, and the Analysis of the Vibrodynamic Processes in a Nuclear Power Plant with a VVER-1000

M. Gholampour, K. N. Proskouriakov

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 311-320

Technical Paper / dx.doi.org/10.13182/NSE159-311

Tritium-Charged Capacitor

A. Kavetsky, G. Yakubova, M. Sychov, Q. Lin, G. Walter, D. Chan, S. Yousaf, H. Socarras, J. Abrefah, K. Bower

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 321-329

Technical Paper / dx.doi.org/10.13182/NSE159-321

A Quasi-Linear Implementation of High-Resolution Time Integration for the P_n Equations

Ryan G. McClarren, James Paul Holloway

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 330-337

Technical Note / dx.doi.org/10.13182/NSE159-330

Two Media Method: An Alternative Methodology for the Measurement of Attenuation Coefficients of Irregularly Shaped Samples

Sukhpal Singh, Gurmel S. Mudahar, Ashok Kumar, Kulwant Singh Thind

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 338-345

Technical Note / dx.doi.org/10.13182/NSE159-338

A Fission Chamber Measurement of the ^natB(d,n) Cross Section for Use in Neutron Detector Calibration

A. R. Di Lullo, T. N. Massey, S. M. Grimes, D. E. Carter, J. E. O'Donnell, D. Jacobs

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 346-350

Technical Note / dx.doi.org/10.13182/NSE159-346TN