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Volume 167

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Table of Contents

Nuclear Science and Engineering / Volume 167 / Number 1

January 2011

Table of Contents

Nuclear Science and Engineering / Volume 167 / Number 2

February 2011

Table of Contents

Nuclear Science and Engineering / Volume 167 / Number 3

March 2011

Exploration of an Analytical Model for Treating the Unresolved Resonances

R. N. Hwang

Nuclear Science and Engineering / Volume 167 / Number 1 / Pages 1-39

January 2011

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An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport Codes

Pietro Mosca, Claude Mounier, Richard Sanchez, Gilles Arnaud

Nuclear Science and Engineering / Volume 167 / Number 1 / Pages 40-60

January 2011

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Reactor Kinetics, Dynamic Response, and Neutron Noise in Molten Salt Reactors

I. Pázsit, A. Jonsson

Nuclear Science and Engineering / Volume 167 / Number 1 / Pages 61-76

January 2011

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A Five-Year Core for a Small Modular Light Water Reactor

Alexey Soldatov, Todd S. Palmer

Nuclear Science and Engineering / Volume 167 / Number 1 / Pages 77-90

January 2011

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A Zero-Variance-Based Scheme for Monte Carlo Criticality Calculations

Stavros Christoforou, J. Eduard Hoogenboom

Nuclear Science and Engineering / Volume 167 / Number 1 / Pages 91-104

January 2011

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Analysis of Coolant Void Reactivity of Advanced Heavy Water Reactor Through Isotopic Reaction Rates

Kannan Umasankari, S. Ganesan

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 105-121

February 2011

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Application of the Jacobian-Free Newton-Krylov Method to Nonlinear Acceleration of Transport Source Iteration in Slab Geometry

D. A. Knoll, H. Park, Kord Smith

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 122-132

February 2011

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Acceleration of k-Eigenvalue/Criticality Calculations Using the Jacobian-Free Newton-Krylov Method

D. A. Knoll, H. Park, C. Newman

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 133-140

February 2011

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Newton's Method for Solving k-Eigenvalue Problems in Neutron Diffusion Theory

Daniel F. Gill, Yousry Y. Azmy

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 141-153

February 2011

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Comparison of Different Numerical Methods Used in Delayed Neutron Decay Parameters Estimation

Jinkai Wang, Warren D. Reece

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 154-164

February 2011

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Biases and Statistical Errors in Monte Carlo Burnup Calculations: An Unbiased Stochastic Scheme to Solve Boltzmann/Bateman Coupled Equations

E. Dumonteil, C. M. Diop

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 165-170

February 2011

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Calculation of the (, n) Emission from Plutonium Nitrate and Plutonium Uranyl Nitrate Solutions

M. T. Swinhoe

Nuclear Science and Engineering / Volume 167 / Number 2 / Pages 171-175

February 2011

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

Nicolas Martin, Alain Hébert

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

March 2011

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Uncertainty Propagation in Monte Carlo Depletion Analysis

Ho Jin Park, Hyung Jin Shim, Chang Hyo Kim

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

March 2011

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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 / Pages 209-220

March 2011

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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 / Pages 221-229

March 2011

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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 / Pages 230-241

March 2011

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