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 / dx.doi.org/10.13182/NSE162-01
Application of hp Adaptivity to the Multigroup Diffusion Equations
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 22-48
Technical Paper / dx.doi.org/10.13182/NSE161-22
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 49-67
Technical Paper / dx.doi.org/10.13182/NSE161-49
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 / dx.doi.org/10.13182/NSE161-68
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 78-89
Technical Paper / dx.doi.org/10.13182/NSE07-49
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 / dx.doi.org/10.13182/NSE161-90
The Fast Fission Factor Revisited
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 111-118
Technical Paper / dx.doi.org/10.13182/NSE161-111
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 119-124
Technical Note / dx.doi.org/10.13182/NSE161-119
External Neutron Drive for Subcritical Reactors
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 125-129
Technical Note / dx.doi.org/10.13182/NSE161-125
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 131-159
Technical Paper / dx.doi.org/10.13182/NSE161-131
Review of the CRAC and SILENE Criticality Accident Studies
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 160-187
Technical Paper / dx.doi.org/10.13182/NSE08-15
Fission Product Experimental Program: Validation and Computational Analysis
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 188-215
Technical Paper / dx.doi.org/10.13182/NSE07-86
Coupled Space-Angle Adaptivity for Radiation Transport Calculations
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 216-234
Technical Paper / dx.doi.org/10.13182/NSE161-216
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 / dx.doi.org/10.13182/NSE161-235
Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 245-254
Technical Note / dx.doi.org/10.13182/NSE161-245
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 257-278
Technical Paper / dx.doi.org/10.13182/NSE161-257
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 / dx.doi.org/10.13182/NSE161-279
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 / dx.doi.org/10.13182/NSE161-289
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 / dx.doi.org/10.13182/NSE161-303
Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 321-330
Technical Paper / dx.doi.org/10.13182/NSE161-321
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 / dx.doi.org/10.13182/NSE161-331
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 / dx.doi.org/10.13182/NSE161-346
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 / dx.doi.org/10.13182/NSE161-357
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 / dx.doi.org/10.13182/NSE161-363