Volume 167
Number 1 | Number 2 | Number 3
Number 1
Exploration of an Analytical Model for Treating the Unresolved Resonances
Nuclear Science and Engineering / Volume 167 / Number 1 / January 2011 / Pages 1-39
Technical Paper / dx.doi.org/10.13182/NSE10-004
An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport Codes
Nuclear Science and Engineering / Volume 167 / Number 1 / January 2011 / Pages 40-60
Technical Paper / dx.doi.org/10.13182/NSE10-10
Reactor Kinetics, Dynamic Response, and Neutron Noise in Molten Salt Reactors
Nuclear Science and Engineering / Volume 167 / Number 1 / January 2011 / Pages 61-76
Technical Paper / dx.doi.org/10.13182/NSE10-15
A Five-Year Core for a Small Modular Light Water Reactor
Nuclear Science and Engineering / Volume 167 / Number 1 / January 2011 / Pages 77-90
Technical Paper / dx.doi.org/10.13182/NSE09-39
A Zero-Variance-Based Scheme for Monte Carlo Criticality Calculations
Nuclear Science and Engineering / Volume 167 / Number 1 / January 2011 / Pages 91-104
Technical Paper / dx.doi.org/10.13182/NSE09-107
Number 2
Analysis of Coolant Void Reactivity of Advanced Heavy Water Reactor Through Isotopic Reaction Rates
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 105-121
Technical Paper / dx.doi.org/10.13182/NSE10-17
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 122-132
Technical Paper / dx.doi.org/10.13182/NSE09-75
Acceleration of k-Eigenvalue/Criticality Calculations Using the Jacobian-Free Newton-Krylov Method
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 133-140
Technical Paper / dx.doi.org/10.13182/NSE09-89
Newton's Method for Solving k-Eigenvalue Problems in Neutron Diffusion Theory
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 141-153
Technical Paper / dx.doi.org/10.13182/NSE09-98
Comparison of Different Numerical Methods Used in Delayed Neutron Decay Parameters Estimation
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 154-164
Technical Paper / dx.doi.org/10.13182/NSE09-94
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 165-170
Technical Paper / dx.doi.org/10.13182/NSE09-100
Calculation of the (
, n) Emission from Plutonium Nitrate and Plutonium Uranyl Nitrate Solutions
Nuclear Science and Engineering / Volume 167 / Number 2 / February 2011 / Pages 171-175
Technical Paper / dx.doi.org/10.13182/NSE09-97
Number 3
A Monte Carlo Lattice Code with Probability Tables and Optimized Energy Meshes
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 177-195
Technical Paper / dx.doi.org/10.13182/NSE10-45
Uncertainty Propagation in Monte Carlo Depletion Analysis
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 196-208
Technical Paper / dx.doi.org/10.13182/NSE09-106
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 209-220
Technical Paper / dx.doi.org/10.13182/NSE10-34
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 221-229
Technical Paper / dx.doi.org/10.13182/NSE09-105
Application of CASMO-4/MICROBURN-B2 Methodology to Mixed Cores with Westinghouse Optima2 Fuel
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 230-241
Technical Paper / dx.doi.org/10.13182/NSE10-18
Effects of He++ Ion Irradiation on Adhesion of Polymer Microstructure-Based Dry Adhesives
Nuclear Science and Engineering / Volume 167 / Number 3 / March 2011 / Pages 242-247
Technical Note / dx.doi.org/10.13182/NSE10-56TN
