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Volume 84

Number 1

Measurement of the 242mAm Neutron Fission Cross Section

J. W. T. Dabbs, C. E. Bemis, Jr., S. Raman, R. J. Dougan, R. W. Hoff

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE83-A17453

Neutron-Induced Gamma-Ray Production in 57Fe for Incident Neutron Energies Between 0.16 and 21 MeV

Z. W. Bell, J. K. Dickens, D. C. Larson, J. H. Todd

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 12-32

Technical Paper / dx.doi.org/10.13182/NSE83-A17454

The Solution of the Multigroup Neutron Transport Equation Using Spherical Harmonics

J. K. Fletcher

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 33-46

Technical Paper / dx.doi.org/10.13182/NSE83-A17455

Thermal Performance Modeling of Sphere-Pac Mixed Carbide Fast Reactor Fuel

M. J. Ades, K. L. Peddicord, S. D. Montgomery

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 47-58

Technical Note / dx.doi.org/10.13182/NSE83-A17456

Real-Time Nonlinear Estimation of Fuel-Clad Gap Conductance

J. Louis Tylee

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 58-61

Technical Note / dx.doi.org/10.13182/NSE83-A17457

Benchmark Values for Monoenergetic Neutron Transport in One-Dimensional Cylindrical Geometry with Linearly Anisotropic Scattering

R. Sanchez, B. D. Ganapol

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 61-66

Technical Note / dx.doi.org/10.13182/NSE83-A17458

Two Vectorized Algorithms for the Solution of Three-Dimensional Neutron Diffusion Equations

Wm. A. Thomas, E. E. Lewis

Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 67-71

Technical Note / dx.doi.org/10.13182/NSE83-A17459