Number 1 | Number 2 | Number 3
Recycling-Independent Core Design for the ENHS Fuel Self-Sustaining Reactor
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 1-21
Technical Paper
Application of hp Adaptivity to the Multigroup Diffusion Equations
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 22-48
Technical Paper
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 49-67
Technical Paper
Reducing Parasitic Thermal Neutron Absorption in Graphite Reactors by 30%
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 68-77
Technical Paper
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 78-89
Technical Paper
Calculation and Evaluations for n + 54,56,57,58,natFe Reactions
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 90-110
Technical Paper
The Fast Fission Factor Revisited
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 111-118
Technical Paper
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 119-124
Technical Note
External Neutron Drive for Subcritical Reactors
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 125-129
Technical Note
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 131-159
Technical Paper
Review of the CRAC and SILENE Criticality Accident Studies
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 160-187
Technical Paper
Fission Product Experimental Program: Validation and Computational Analysis
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 188-215
Technical Paper
Coupled Space-Angle Adaptivity for Radiation Transport Calculations
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 216-234
Technical Paper
The Impact of Core Flow Rate on the Hydrogen Water Chemistry Efficiency in Boiling Water Reactors
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 235-244
Technical Paper
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 245-254
Technical Note
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 257-278
Technical Paper
A New Paradigm for Local-Global Coupling in Whole-Core Neutron Transport
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 279-288
Technical Paper
Effect of 24195Am(n,
) Reaction Branching Ratio on Fuel Cycle and Reactor Design Characteristics
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 289-302
Technical Paper
Hafnium Resonance Parameter Analysis Using Neutron Capture and Transmission Experiments
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 303-320
Technical Paper
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 321-330
Technical Paper
Theoretical Calculations and Analysis for the n + 59Co Reaction up to 20 MeV
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 331-345
Technical Paper
Scaling Relations for Intermediate-Energy Proton-Nucleus Reactions with Small Energy Losses
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 346-356
Technical Paper
Subcritical Measurements of a Plutonium Sphere Reflected by Polyethylene and Acrylic
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 357-362
Technical Paper
A Monte Carlo Approach to Nuclear Model Parameter Uncertainties Propagation
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 363-370
Technical Paper