Numerical Methods of High Order Accuracy for One-Dimensional Diffusion Equation
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 185-199
Technical Paper / dx.doi.org/10.13182/NSE73-A28971
The Neutron Diffusion Coefficient as a Second-Order Tensor—Theory and Calculations
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 200-207
Technical Paper / dx.doi.org/10.13182/NSE73-A28972
Delayed Neutron Data for Fast Reactor Analysis
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 208-215
Technical Paper / dx.doi.org/10.13182/NSE73-A28973
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 216-219
Technical Paper / dx.doi.org/10.13182/NSE73-A28974
A Bilinear Formulation for Spatial Cross-Section Averaging
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 220-228
Technical Paper / dx.doi.org/10.13182/NSE73-A28975
A Study of Several Methods for Analysis of Critical Assembly Heterogeneity
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 229-242
Technical Paper / dx.doi.org/10.13182/NSE73-A28976
The Total Neutron Cross Sections of Uranium-238 from 0.8 to 30 MeV
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 243-247
Technical Paper / dx.doi.org/10.13182/NSE73-A28977
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 248-256
Technical Paper / dx.doi.org/10.13182/NSE73-A28978
The Californium-252 Fission Neutron Spectrum from 0.5 to 13 MeV
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 257-272
Technical Paper / dx.doi.org/10.13182/NSE73-A28979
A Study of Fission-Fragment-Induced Nucleation of Bubbles in Superheated Water
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 273-282
Technical Paper / dx.doi.org/10.13182/NSE73-A28980
Thermal Contact Conductance in Reactor Fuel Elements
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 283-290
Technical Note / dx.doi.org/10.13182/NSE73-A28981
Errors in Perturbation Calculations
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 290-293
Technical Note / dx.doi.org/10.13182/NSE73-A28982
Second-Order Boltzmann Equation from Invariant Imbedding Theory
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 294-297
Technical Note / dx.doi.org/10.13182/NSE73-A28983
Computational Experimentation on the Finite Element Method in Bare Slab Criticality Calculations
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 297-300
Technical Note / dx.doi.org/10.13182/NSE73-A28984
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 300-302
Technical Note / dx.doi.org/10.13182/NSE73-A28985
In-Core Neutron Flux Distribution Measurement by a Circulating Fluid Activation Method
Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 302-306
Technical Note / dx.doi.org/10.13182/NSE73-A28986