Volume 53
Number 1
Measurements of the 59Ni(n,α) Cross Section for Thermal Neutrons
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 1-8
Technical Paper / dx.doi.org/10.13182/NSE74-A23326
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 9-26
Technical Paper / dx.doi.org/10.13182/NSE74-A23327
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 27-46
Technical Paper / dx.doi.org/10.13182/NSE74-A23328
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 47-60
Technical Paper / dx.doi.org/10.13182/NSE74-A23329
Model for Calculating Prompt-Response Self-Powered Neutron Detectors
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 61-78
Technical Paper / dx.doi.org/10.13182/NSE74-A23330
A Criticality Study of Fissile-Metal and Fissile-Solution Combinations
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 79-92
Technical Paper / dx.doi.org/10.13182/NSE74-A23331
Numerical Solution of the Linear Integral Boltzmann Equation
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 93-106
Technical Paper / dx.doi.org/10.13182/NSE74-A23332
The Permeability Minimum and the Viscosity of Gases at Low Pressure
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 107-109
Technical Paper / dx.doi.org/10.13182/NSE74-A23333
Calculated and Measured Dose Buildup Factors for Gamma Rays Penetrating Multilayered Slabs
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 109-112
Technical Paper / dx.doi.org/10.13182/NSE74-A23334
Modified One-Mode Method for Fast-Reactor Diffusion Calculations
Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 112-120
Technical Paper / dx.doi.org/10.13182/NSE74-A23335
