A New Approximation for the Neutron Albedo
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 1-17
Technical Paper / dx.doi.org/10.13182/NSE07-A2641
Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 18-36
Technical Paper / dx.doi.org/10.13182/NSE06-11
Multigroup Adjoint Transport Solution Using the Method of Cyclic Characteristics
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 37-52
Technical Paper / dx.doi.org/10.13182/NSE07-A2643
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 53-73
Technical Paper / dx.doi.org/10.13182/NSE07-A2644
Neutron Scattering from an Asymmetric Rotor: 197Au
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 74-83
Technical Paper / dx.doi.org/10.13182/NSE07-A2645
Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 84-95
Technical Paper / dx.doi.org/10.13182/NSE07-A2646
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 96-101
Technical Paper / dx.doi.org/10.13182/NSE07-A2647
Studies on Effective Atomic Numbers and Electron Densities in Some Commonly Used Solvents
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 102-108
Technical Paper / dx.doi.org/10.13182/NSE07-A2648
Polynomial Chaos Functions and Neutron Diffusion
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 109-118
Technical Note / dx.doi.org/10.13182/NSE05-73TN
A New Approach to Spatio-Temporal Calculation of Nuclear Reactor Cores Using Neural Computing
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 119-130
Technical Note / dx.doi.org/10.13182/NSE07-A2650
Monte Carlo Modeling of Delayed Neutrons from Photofission
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 131-142
Technical Note / dx.doi.org/10.13182/NSE07-A2651
Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 143-153
Computer Code Abstract / dx.doi.org/10.13182/NSE07-A2652