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Volume 167

Number 3

A Monte Carlo Lattice Code with Probability Tables and Optimized Energy Meshes

Nicolas Martin, Alain Hébert

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 177-195

Technical Paper

Uncertainty Propagation in Monte Carlo Depletion Analysis

Ho Jin Park, Hyung Jin Shim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 196-208

Technical Paper

Reactivity Perturbation Formulation for a Discontinuous Galerkin-Based Transport Solver and Its Use with Adaptive Mesh Refinement

R. Le Tellier, D. Fournier, C. Suteau

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 209-220

Technical Paper

Simulations and Models of Neutron Fluxes in Boiling Water Reactors Intended for Depletion Calculations of Withdrawn Control Rods

John Loberg, Michael Österlund, Klaes-Håkan Bejmer, Jan Blomgren, Jesper Kierkegaard, Sten-Örjan Lindahl

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 221-229

Technical Paper

Application of CASMO-4/MICROBURN-B2 Methodology to Mixed Cores with Westinghouse Optima2 Fuel

Ming-Yuan Hsiao, John K. Wheeler, Carlos de la Hoz

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 230-241

Technical Paper

Effects of He++ Ion Irradiation on Adhesion of Polymer Microstructure-Based Dry Adhesives

Paul Day, Mark Cutkosky, Richard Greco, Anastasia McLaughlin

Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 242-247

Technical Note

 
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