Volume 45
Number 1 | Number 2 | Number 3
Number 1
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 1-6
Technical Paper / dx.doi.org/10.13182/NSE71-A20339
The Exact Probability Distribution of Reactor Neutron Noise
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 7-13
Technical Paper / dx.doi.org/10.13182/NSE71-A20340
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 14-24
Technical Paper / dx.doi.org/10.13182/NSE71-A20341
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 25-36
Technical Paper / dx.doi.org/10.13182/NSE71-A20342
An Integral Measurement of Plutonium-239 and Uranium-233 Alpha
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 37-46
Technical Paper / dx.doi.org/10.13182/NSE71-A20343
Photofission Cross Section of Plutonium-238 and Plutonium-239
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 47-51
Technical Paper / dx.doi.org/10.13182/NSE71-A20344
The Fuel Cycle Analysis System, REBUS
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 52-65
Technical Paper / dx.doi.org/10.13182/NSE71-1
Weighting and Biasing of a Monte Carlo Calculation for Very Deep Penetration of Radiation
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 66-72
Technical Paper / dx.doi.org/10.13182/NSE71-A20346
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 73-85
Technical Paper / dx.doi.org/10.13182/NSE71-A20347
An Observation on the Material Bucklings of the Multigroup Diffusion Equations
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 86-87
Technical Note / dx.doi.org/10.13182/NSE71-A20348
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 87-94
Technical Note / dx.doi.org/10.13182/NSE71-A20349
Effective Atomic Numbers for Photoelectric and Incoherent Scattering Processes of Gamma Rays
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 94-97
Technical Note / dx.doi.org/10.13182/NSE71-A20350
Optical Detection of Boiling in Pressurized Water Reactors
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 97-99
Technical Note / dx.doi.org/10.13182/NSE71-A20351
Anisothermal Effects During In-Pile Creep Testing of Uranium Dioxide
Nuclear Science and Engineering / Volume 45 / Number 1 / July 1971 / Pages 99-102
Technical Note / dx.doi.org/10.13182/NSE71-A20352
Number 2
A Method for Solving Time-Dependent Electron Transport Problems
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 107-116
Technical Paper / dx.doi.org/10.13182/NSE71-A20878
Beam Enrichment by the Multilayered Neutron-Reflecting Conical Tube
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 117-125
Technical Paper / dx.doi.org/10.13182/NSE71-A20879
Slow-Neutron Scattering by Light and Heavy Water
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 126-140
Technical Paper / dx.doi.org/10.13182/NSE71-A20880
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 141-155
Technical Paper / dx.doi.org/10.13182/NSE71-A20881
The Degenerate Kernel Technique and Neutron Thermalization Calculations in Asymptotic Reactor Theory
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 156-166
Technical Paper / dx.doi.org/10.13182/NSE71-A20882
Applications of the Degenerate Kernel Technique to Thermal Neutron Spectra Calculations
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 167-181
Technical Paper / dx.doi.org/10.13182/NSE71-A20883
P1 Blackness Theory for Infinite Cylinders
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 182-188
Technical Paper / dx.doi.org/10.13182/NSE71-A20884
Solution of the Neutron Diffusion Equation by Space-Energy Factorization
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 189-198
Technical Paper / dx.doi.org/10.13182/NSE71-A20885
Optimal Control of Nuclear Reactor Depletion
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 199-217
Technical Paper / dx.doi.org/10.13182/NSE71-A20886
Radiation Effects on Superheating of Liquid Sodium
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 218-221
Technical Note / dx.doi.org/10.13182/NSE71-A20887
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 221-226
Technical Note / dx.doi.org/10.13182/NSE71-A20888
Analytic Solution to the Flat Flux Problem
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 226-230
Technical Note / dx.doi.org/10.13182/NSE71-A20889
Calculations of Thermal-Neutron Group Constants During Burnup of Light-Water-Moderated Lattices
Nuclear Science and Engineering / Volume 45 / Number 2 / August 1971 / Pages 230-232
Technical Note / dx.doi.org/10.13182/NSE71-A20890
Number 3
Integral Transport Theory Analysis of Central Reactivity Worth Measurements
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 237-244
Technical Paper / dx.doi.org/10.13182/NSE71-A19076
The Effectiveness of Acceleration Techniques for Iterative Methods in Transport Theory
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 245-254
Technical Paper / dx.doi.org/10.13182/NSE71-A19077
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 255-268
Technical Paper / dx.doi.org/10.13182/NSE45-03-255
Group Transfer Matrices and Their Relation to Basic Cross Section Data
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 269-278
Technical Paper / dx.doi.org/10.13182/NSE71-A19079
Cross Sections in the Unresolved Resonance Region: Methods and Evaluation of Approximations
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 279-296
Technical Paper / dx.doi.org/10.13182/NSE71-A19080
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 297-307
Technical Paper / dx.doi.org/10.13182/NSE71-A19081
Thermal-Neutron Diffusion Parameters in Water by the Poisoning Method
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 308-313
Technical Paper / dx.doi.org/10.13182/NSE71-A19082
Neutronic-Acoustic Detection of the Onset of Bulk Boiling in Liquid Sodium
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 314-320
Technical Paper / dx.doi.org/10.13182/NSE71-A19083
Evaluation of Grain Shielding Factors for Coated Fuel Particles
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 321-330
Technical Paper / dx.doi.org/10.13182/NSE71-A19084
Matrix Reimann-Hilbert Problems Related to Neutron Transport Theory
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 331-332
Technical Note / dx.doi.org/10.13182/NSE71-A19085
The Effect of Condensing the Spatial Mesh on the Accuracy of Fast Breeder Fuel-Cycle Analyses
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 333-335
Technical Note / dx.doi.org/10.13182/NSE71-A19086
Kinetic Distortion in a TRIGA Reactor with an Asymmetric Reflector
Nuclear Science and Engineering / Volume 45 / Number 3 / September 1971 / Pages 335-341
Technical Note / dx.doi.org/10.13182/NSE71-2
