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Volume 59

Number 2

Fast-Neutron Total and Scattering Cross Sections of Elemental Nickel

P. Guenther, A. Smith, J. Whalen

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

F. Schmittroth

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

William T. Sha, Robert C. Schmitt, P. R. Huebotter

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

Kazuyoshi Miki, Kotaro Inoue

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

J. P. Hennart, B. Torres Barrios

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

E. M. Oblow

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

R. T. Santoro, J. Barish

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

D. Stefanović

Nuclear Science and Engineering / Volume 59 / Number 2 / February 1976 / Pages 194-198

Technical Note / dx.doi.org/10.13182/NSE76-A15690