Mass-Fission-Yield Curve for Americium-241
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 115-118
Technical Paper / dx.doi.org/10.13182/NSE65-A28135
Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part I
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 119-129
Technical Paper / dx.doi.org/10.13182/NSE65-A28136
Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part II
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 130-137
Technical Paper / dx.doi.org/10.13182/NSE65-A28137
Differential Dose-Rate Measurements of Backscattered Gamma Rays from Concrete, Aluminum and Steel
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 138-149
Technical Paper / dx.doi.org/10.13182/NSE65-A28138
Criticality of Homogeneous Plutonium Oxide-Plastic Compacts at H:Pu=15
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 150-158
Technical Paper / dx.doi.org/10.13182/NSE65-A28139
The Decay of Equilibrium Neutron Flux Inside Beryllium Blocks at Different Temperatures
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 159-166
Technical Paper / dx.doi.org/10.13182/NSE65-A28140
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 167-169
Technical Paper / dx.doi.org/10.13182/NSE65-A28141
New Approximate Solution of Space- and Energy-Dependent Reactor Kinetics
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 170-182
Technical Paper / dx.doi.org/10.13182/NSE65-A28142
A Simplified Nonlinear Model for Qualitative Study of Reactor Power-Distribution Transients
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 183-187
Technical Paper / dx.doi.org/10.13182/NSE65-A28143
Nuclear-Fuel-Depletion Measuring Device
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 188-189
Technical Note / dx.doi.org/10.13182/NSE65-A28144
Fission-Product Effects in Molten Chloride Fast-Reactor Fuels
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 189-190
Technical Note / dx.doi.org/10.13182/NSE65-A28145
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 190-192
Technical Note / dx.doi.org/10.13182/NSE65-A28146
The Energy-Dependent Total Neutron Cross Section of Polyethylene
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 192-194
Technical Note / dx.doi.org/10.13182/NSE65-A28147
Inelastic Scattering of Slow Neutrons by Zirconium and Titanium Hydrides
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 194-197
Technical Note / dx.doi.org/10.13182/NSE65-A28148
Some Remarks on the Reduction of Thermal-Neutron Activation Rates to a Differential Spectrum
Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 197-199
Technical Note / dx.doi.org/10.13182/NSE65-A28149