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Volume 162

Number 3

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 SN-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