Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 159-164
Technical Paper / dx.doi.org/10.13182/NSE67-A18523
Correlation of Radiation Damage to Steel with Neutron Spectrum
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 165-175
Technical Paper / dx.doi.org/10.13182/NSE67-A18524
Buffering of Uranium Monocarbide to Control Carbon Activity
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 176-179
Technical Paper / dx.doi.org/10.13182/NSE67-A18525
An Intrinsic Method for Determining Absolute Thermal Flux and Power in Heterogeneous Reactors
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 180-188
Technical Paper / dx.doi.org/10.13182/NSE67-A18526
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 189-197
Technical Paper / dx.doi.org/10.13182/NSE67-A18527
Spatial Dependence of Slowing Down Times for 14.1-MeV Neutrons in Water
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 198-209
Technical Paper / dx.doi.org/10.13182/NSE67-A18528
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 210-217
Technical Paper / dx.doi.org/10.13182/NSE67-A18529
Capture Cross Sections of Neptunium-237
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 218-219
Technical Paper / dx.doi.org/10.13182/NSE67-A18530
A Derivation of Variational Principles for Inhomogeneous Equations
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 220-236
Technical Paper / dx.doi.org/10.13182/NSE67-A18531
Singular Difference Approximations for the Discrete Ordinate Equations in x-y Geometry
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 237-243
Technical Paper / dx.doi.org/10.13182/NSE67-A18532
Concerning Infinitely Dilute Resonance Integrals
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 244-247
Technical Paper / dx.doi.org/10.13182/NSE67-A18533
One-Speed Neutron Transport in Slab Geometry
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 248-253
Technical Paper / dx.doi.org/10.13182/NSE67-A18534
Spectrum and Importance Function in Spatially Independent Fast-Reactor Assemblies
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 254-263
Technical Paper / dx.doi.org/10.13182/NSE67-A18535
State Variable Feedback Control of Multiregion Reactors
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 264-271
Technical Paper / dx.doi.org/10.13182/NSE67-A18536
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 272-282
Technical Paper / dx.doi.org/10.13182/NSE67-3
Interpretation of Pulsed-Source Experiments in the Peach Bottom HTGR
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 283-295
Technical Paper / dx.doi.org/10.13182/NSE67-4
Buckling Measurements in Water-Moderated and -Reflected Exponential Experiments
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 296-298
Technical Note / dx.doi.org/10.13182/NSE67-A18539
The Mismatch of Thermal and Epithermal Neutron Flux
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 299-302
Technical Note / dx.doi.org/10.13182/NSE67-A18540
Solutions of the Time-Dependent One-Group Diffusion Equations for Reflected Systems
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 302-305
Technical Note / dx.doi.org/10.13182/NSE67-A18541
The Extrapolated Endpoint for the Milne Problem
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 305-308
Technical Note / dx.doi.org/10.13182/NSE67-A18542
Subcritical Reactivity from Neutron Statistics
Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 308-310
Technical Note / dx.doi.org/10.13182/NSE67-A18543