Measurement of the 242mAm Neutron Fission Cross Section
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
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
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
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
Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 58-61
Technical Note / dx.doi.org/10.13182/NSE83-A17457
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
Nuclear Science and Engineering / Volume 84 / Number 1 / May 1983 / Pages 67-71
Technical Note / dx.doi.org/10.13182/NSE83-A17459