ANS / Publications / Journals / Nuclear Science and Engineering

HTC Experimental Program: Validation and Calculational Analysis

F. Fernex, T. Ivanova, F. Bernard, E. Latang, P. Fouillaud, J. F. Thro

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 1-24

Technical Paper / dx.doi.org/10.13182/NSE07-52

Extensive Set of Cross-Section Covariance Estimates in the Fast Neutron Region

M. T. Pigni, M. Herman, P. Oblozinsky

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 25-40

Technical Paper / dx.doi.org/10.13182/NSE162-25

Spatial Convergence Study of Discrete Ordinates Methods Via the Singular Characteristic Tracking Algorithm

J. I. Duo, Y. Y. Azmy

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 41-55

Technical Paper / dx.doi.org/10.13182/NSE08-28

Development of the Subgroup Projection Method for Resonance Self-Shielding Calculations

Alain Hébert

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 56-75

Technical Paper / dx.doi.org/10.13182/NSE162-56

Generalization of the SPRT Method for the Modeling of the Neutron Cross Sections in the Unresolved Resonance Range

E. Rich, Gilles Noguere, C. De Saint Jean, A. Tudora

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 76-86

Technical Paper / dx.doi.org/10.13182/NSE162-76

Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor

Ned Xoubi, R. T. Primm III, G. Ivan Maldonado

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 87-97

Technical Paper / dx.doi.org/10.13182/NSE162-87

Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations

Hyung Jin Shim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 98-108

Technical Paper / dx.doi.org/10.13182/NSE09-2

Inverse Generalized Perturbation Theory in Reactor Core Constrained Calculations

Aldo Dall'Osso

Nuclear Science and Engineering / Volume 162 / Number 1 / May 2009 / Pages 109-116

Technical Paper / dx.doi.org/10.13182/NSE162-109

Feynman-Alpha and Rossi-Alpha Formulas with Delayed Neutrons for Subcritical Reactors Driven by Pulsed Non-Poisson Sources

Y. S. Rana, S. B. Degweker

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 117-133

Technical Papers / dx.doi.org/10.13182/NSE08-13

Multiobjective Loading Pattern Optimization by Simulated Annealing Employing Discontinuous Penalty Function and Screening Technique

Tong Kyu Park, Han Gyu Joo, Chang Hyo Kim, Hyun Chul Lee

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 134-147

Technical Paper / dx.doi.org/10.13182/NSE162-134

Nuclear Fuel Lattice Optimization Using Neural Networks and a Fuzzy Logic System

Juan José Ortiz, Alejandro Castillo, José Luis Montes, Raúl Perusquía, José Luis Hernández

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 148-157

Technical Paper / dx.doi.org/10.13182/NSE162-148

An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source

Kirill Fedorovich Raskach

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 158-166

Technical Paper / dx.doi.org/10.13182/NSE162-158

Various Operating Regimes of a Subcritical System as a Function of Subcriticality in One-Group Theory

P. Saracco, G. Ricco

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 167-177

Technical Note / dx.doi.org/10.13182/NSE162-167

Modeling of the n + ²⁴²Pu Reactions for Fast Reactor Applications

E. Rich, A. Tudora, G. Noguere, J. Tommasi, J.-F. Lebrat

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 178-191

Technical Note / dx.doi.org/10.13182/NSE162-178

New Properties and Approximations of Doppler Broadening Functions Using Steffensen's Inequality

R. S. Keshavamurthy, R. S. Geetha

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 192-199

Technical Note / dx.doi.org/10.13182/NSE162-192

Performance of an Automated Digital Gamma-Imaging System Based upon Cadmium Telluride-Complementary Metal-Oxide Semiconductor Sensor and Collimated ⁷⁵Se Source for Nondestructive Testing

B. S. Kang, H. S. Cho, S. Y. Lee, S. I. Choi, J. E. Oh, H. M. Cho

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 200-207

Technical Note / dx.doi.org/10.13182/NSE162-200

Evaluation of Self-Protection of 20% Uranium Denatured with ²³²U Against Unauthorized Reenrichment

E. F. Kryuchkov, V. A. Apse, V. A.Yufereva, V. B. Glebov, A. N. Shmelev

Nuclear Science and Engineering / Volume 162 / Number 2 / June 2009 / Pages 208-213

Technical Note / dx.doi.org/10.13182/NSE162-208

Error Analysis of the Nodal Integral Method for Solving the Neutron Diffusion Equation in Two-Dimensional Cartesian Geometry

R. M. Ferrer, Y. Y. Azmy

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 215-233

Technical Paper / dx.doi.org/10.13182/NSE162-215

Properties of the S_N-Equivalent Integral Transport Operator in Slab Geometry and the Iterative Acceleration of Neutral Particle Transport Methods

Massimiliano Rosa, Yousry Y. Azmy, Jim E. Morel

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 234-252

Technical Paper / dx.doi.org/10.13182/NSE162-234

Measurement of the Thermal Absorption Cross Section in Lucite Using Fermi Age Theory

Rene Sanchez, John Bounds, David Hayes, Travis Grove, Fredrik Tovesson

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 253-260

Technical Paper / dx.doi.org/10.13182/NSE162-253

Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D

W. R. Marcum, B. G. Woods, M. R. Hartman, S. R. Reese, T. S. Palmer, S. T. Keller

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 261-274

Technical Paper / dx.doi.org/10.13182/NSE08-63

Multiobjective Optimization of the Plate Element of Egyptian Research Reactor Using Genetic Algorithm

Mohamed El-Sayed Wahed, Wesam Zakaria Ibrahim, Ahmed Mostafa Effat

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 275-281

Technical Paper / dx.doi.org/10.13182/NSE162-275

Analysis of Pebble-Fueled Zone Modeling Influence on High-Temperature Reactor Core Calculations

E. Bomboni, N. Cerullo, G. Lomonaco

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 282-298

Technical Note / dx.doi.org/10.13182/NSE162-282

Some Notes on the Definition of Performance Parameters for Reactors and Fuel Cycles

W. F. G. van Rooijen

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 299-306

Technical Note / dx.doi.org/10.13182/NSE162-299

Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors

Jan Dufek, J. Eduard Hoogenboom

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 307-311

Technical Note / dx.doi.org/10.13182/NSE08-69TN

Absolute Total np and pp Cross-Section Determinations

R. A. Arndt, W. J. Briscoe, A. B. Laptev, I. I. Strakovsky, R. L. Workman

Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 312-318

Technical Note / dx.doi.org/10.13182/NSE162-312