Volume 54
Number 4
Generalized Collision Probabilities and Neutron Transport Eigenvalue Problems
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 369-375
Technical Paper / dx.doi.org/10.13182/NSE74-A23431
Weighted Central Difference Equations for the Neutron Transport Equation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 376-386
Technical Paper / dx.doi.org/10.13182/NSE74-A23432
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 387-394
Technical Paper / dx.doi.org/10.13182/NSE74-A23433
Neutron and Gamma-Ray Effects on Self-Powered In-Core Radiation Detectors
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 395-415
Technical Paper / dx.doi.org/10.13182/NSE74-A23434
Small-Angle Scattering of 7.4- to 9.5-MeV Neutrons from Nitrogen and Oxygen
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 416-422
Technical Paper / dx.doi.org/10.13182/NSE74-A23435
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 423-431
Technical Paper / dx.doi.org/10.13182/NSE74-A23436
Accurate Kinetics Equations of a Square Cascade for Gas Separation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 432-444
Technical Paper / dx.doi.org/10.13182/NSE74-A23437
Turbulence Measurements in a Magneto-Fluid-Mechanic Channel
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 445-449
Technical Paper / dx.doi.org/10.13182/NSE74-A23438
Partial-Range Analysis of the One-Speed Neutron Transport Equation with Anisotropic Scattering
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 450-455
Technical Note / dx.doi.org/10.13182/NSE74-A23439
An Asymptotic Solution in the Theory of Neutron Moderation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 455-456
Technical Note / dx.doi.org/10.13182/NSE74-A23440
Application of the Finite Element Method to Two-Dimensional Diffusion Problems
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 456-465
Technical Note / dx.doi.org/10.13182/NSE74-A23441
A Rapid Calculational Method for Multigroup Elastic Transfer
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 465-467
Technical Note / dx.doi.org/10.13182/NSE74-A23442
On the Estimation of Errors in Reactor Theory
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 467-470
Technical Note / dx.doi.org/10.13182/NSE74-A23443
Neutron Yields from Uranium Isotopes in Uranium Hexafluoride
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 470-474
Technical Note / dx.doi.org/10.13182/NSE54-470
Optimization of Control-Rod Programming in Multiregion Nuclear Reactors
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 474-481
Technical Note / dx.doi.org/10.13182/NSE74-A23445
On the Mechanisms for Vapor Explosions
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 481-482
Technical Note / dx.doi.org/10.13182/NSE74-A23446
