Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 79-105
Technical Paper / dx.doi.org/10.13182/NSE76-A15682
Fast-Neutron Total and Scattering Cross Sections of Elemental Nickel
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 106-116
Technical Paper / dx.doi.org/10.13182/NSE76-A15683
Uncertainty Analysis of Fission-Product Decay-Heat Summation Methods
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 117-139
Technical Paper / dx.doi.org/10.13182/NSE76-A15684
Boundary-Value Thermal-Hydraulic Analysis of a Reactor Fuel Rod Bundle
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 140-160
Technical Paper / dx.doi.org/10.13182/NSE76-A15685
A Monte Carlo Code for the Evaluation of the Thermal Design of a Nuclear Reactor Core
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 161-169
Technical Paper / dx.doi.org/10.13182/NSE76-A15686
Generalized Padé and Chebyshev Approximations for Point Kinetics
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 170-187
Technical Note / dx.doi.org/10.13182/NSE76-A15687
Sensitivity Theory from a Differential Viewpoint
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 187-189
Technical Note / dx.doi.org/10.13182/NSE76-A15688
Cross-Section Sensitivity of the D-T Fusion Probability and the D-T and T-T Reaction Rates
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 189-194
Technical Note / dx.doi.org/10.13182/NSE76-A15689
Neutron Slowing Down with Energy-Dependent Anisotropy of Scattering
Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 194-198
Technical Note / dx.doi.org/10.13182/NSE76-A15690