Few-Group Approximations Based on a Variational Principle
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 493-510
Technical Paper / dx.doi.org/10.13182/NSE86-A17615
The Thermal-Neutron Milne Problem with a Two-Term Degenerate Kernel
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 511-519
Technical Paper / dx.doi.org/10.13182/NSE86-A17616
Scattering Functions for Low-Energy Neutron Collisions in a Maxwellian Monatomic Gas
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 520-532
Technical Paper / dx.doi.org/10.13182/NSE86-A17617
Neutron-Flux Spectral Determination by Foil Activation
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 533-541
Technical Paper / dx.doi.org/10.13182/NSE86-A17618
Continuity Conditions for a Homogeneous or Heterogeneous PN Approximation
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 542-548
Technical Paper / dx.doi.org/10.13182/NSE86-A17619
Effects of the Flat-Flux and Infinite-Mass Approximation on Resonance Absorption
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 549-556
Technical Paper / dx.doi.org/10.13182/NSE86-A17620
Multiplication Factor of Uranium Metal by One-Velocity Monte Carlo Calculations
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 557-563
Technical Paper / dx.doi.org/10.13182/NSE86-A17621
The Effect of Air Channels on the Diffusion Length of Thermal Neutrons in Light Water
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 564-567
Technical Paper / dx.doi.org/10.13182/NSE86-A17622
Fission-Neutron Age Measurements in Aluminum-Water Mixtures
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 568-572
Technical Paper / dx.doi.org/10.13182/NSE86-A17623
Experimental Application of the Time-Optimal Xenon Shutdown Program
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 573-580
Technical Paper / dx.doi.org/10.13182/NSE86-A17624
The Influence of Source Geometry on Fission-Fragment Escape Properties
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 581-585
Technical Paper / dx.doi.org/10.13182/NSE86-A17625
Bremsstrahlung from 90Sr-90Y in Thin Absorbers
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 586-596
Technical Paper / dx.doi.org/10.13182/NSE86-A17626
A Method of Calculating Asymptotic and Transient Material Bucklings of a Uniform Rod Lattice
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 597-598
Technical Note / dx.doi.org/10.13182/NSE86-A17627
The Boundary Conditions at the Interface between a Lattice Core and a Homogeneous Reflector
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 598-600
Technical Note / dx.doi.org/10.13182/NSE86-A17628
Controllability of the Spatial Flux Shape
Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 600-604
Technical Note / dx.doi.org/10.13182/NSE86-A17629