Burnup Optimization of Continuous Scattered Refueling
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 1-13
Technical Paper / dx.doi.org/10.13182/NSE70-A20357
A Numerical Method for the Solution of Three-Dimensional Neutron-Transport Problems
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 14-21
Technical Paper / dx.doi.org/10.13182/NSE70-A20358
Extrapolation Distances and Diffusion Parameters via Pulsed-Neutron Analysis
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 22-28
Technical Paper / dx.doi.org/10.13182/NSE70-A20359
An Analytic Representation of Fast-Reactor Neutron-Energy Spectra
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 29-36
Technical Paper / dx.doi.org/10.13182/NSE70-A20360
Estimation of Spatial Distributions of Neutron Captures in Resonance Absorbers
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 37-46
Technical Paper / dx.doi.org/10.13182/NSE70-A20361
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 47-55
Technical Paper / dx.doi.org/10.13182/NSE70-A20362
A Measurement of the Capture-to-Fission Ratio for Plutonium-239
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 56-62
Technical Paper / dx.doi.org/10.13182/NSE70-A20363
Fast-Neutron Total and Scattering Cross Sections of Bismuth
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 63-69
Technical Paper / dx.doi.org/10.13182/NSE70-A20364
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 70-78
Technical Paper / dx.doi.org/10.13182/NSE70-A20365
Two-Phase Critical Flow at Low Qualities Part I: Experimental
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 79-91
Technical Paper / dx.doi.org/10.13182/NSE70-A20366
Two-Phase Critical Flow at Low Qualities Part II: Analysis
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 92-98
Technical Paper / dx.doi.org/10.13182/NSE70-A20367
Theoretical Investigations on Sodium Boiling in Fast Reactors
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 99-114
Technical Paper / dx.doi.org/10.13182/NSE70-A20368
Space-Dependent Dynamic Behavior of Fast Reactors Using the Time-Discontinuous Synthesis Method
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 115-125
Technical Note / dx.doi.org/10.13182/NSE70-A20369
State Variable Feedback and Series Compensation of Multivariate Systems
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 125-129
Technical Note / dx.doi.org/10.13182/NSE70-A20370
Stochastic Stability of a Reactor with Linear Feedback
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 129-132
Technical Note / dx.doi.org/10.13182/NSE70-A20371
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 132-138
Technical Note / dx.doi.org/10.13182/NSE70-A20372
Pulse Neutron Decay in Heavy-Water Spheres
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 138-140
Technical Note / dx.doi.org/10.13182/NSE70-A20373
Legendre Moments of the Elastic-Scattering Cross Section for S-Wave Neutrons
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 140-143
Technical Note / dx.doi.org/10.13182/NSE70-A20374
Derivation of 239Pu Resonance Parameters from Correlation of Experimental Data
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 143-146
Technical Note / dx.doi.org/10.13182/NSE70-A20375
Effective Capture and Fission Cross Sections for Californium-253
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 146-147
Technical Note / dx.doi.org/10.13182/NSE70-A20376
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 147-148
Technical Note / dx.doi.org/10.13182/NSE70-A20377