Particle Transport Calculations with the Method of Streaming Rays
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 119-136
Technical Paper / dx.doi.org/10.13182/NSE81-A21346
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 137-145
Technical Paper / dx.doi.org/10.13182/NSE81-A21347
Yields of Short-Lived Fission Products Produced by Thermal-Neutron Fission of Plutonium-239
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 146-152
Technical Paper / dx.doi.org/10.13182/NSE81-A21348
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 153-156
Technical Paper / dx.doi.org/10.13182/NSE81-A21349
The Distribution of Thermal Neutron Cross Sections
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 157-167
Technical Paper / dx.doi.org/10.13182/NSE81-A21350
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 168-181
Technical Paper / dx.doi.org/10.13182/NSE81-A21351
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 182-191
Technical Paper / dx.doi.org/10.13182/NSE81-A21352
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 192-210
Technical Paper / dx.doi.org/10.13182/NSE81-A21353
The Solubility of Nickel Ferrite in Aqueous Boric Acid Solution
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 211-218
Technical Paper / dx.doi.org/10.13182/NSE81-A21354
Rigorous Homogenized Diffusion Theory Parameters for Neutrons
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 219-229
Technical Note / dx.doi.org/10.13182/NSE81-A21355
An Equivalence Relation for a Lattice of Annular Absorbers
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 229-235
Technical Note / dx.doi.org/10.13182/NSE81-A21356
Reactor Fuel Burnup Calculation for a Square Lattice Cell
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 235-250
Technical Note / dx.doi.org/10.13182/NSE81-A21357
The Effect of Self-Shielding of the Iron Inelastic Scattering Cross Section on Neutron Spectra
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 250-256
Technical Note / dx.doi.org/10.13182/NSE81-A21358
Cross Sections for 19F(n,p)19O and 19F(n,α)16N from Threshold to 9 MeV
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 256-262
Technical Note / dx.doi.org/10.13182/NSE81-A21359
Decay Schemes for Radionuclides of Potential Importance in the Nuclear Fuel Cycle
Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 263-265
Technical Note / dx.doi.org/10.13182/NSE81-A21360