Volume 43
Number 1 | Number 2 | Number 3
Number 1
On the Use of Acoustic Waves in Nuclear Power Reactors to Determine Average Void Fractions
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 1-4
Technical Paper / dx.doi.org/10.13182/NSE71-A21240
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 5-26
Technical Paper / dx.doi.org/10.13182/NSE71-A21241
The Transmission of Xenon-133 Through Activated Charcoal Adsorber Beds
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 27-31
Technical Paper / dx.doi.org/10.13182/NSE71-A21242
Gamma-Ray Attenuation at Energies of Approximately 6 and 8 MeV
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 32-41
Technical Paper / dx.doi.org/10.13182/NSE71-A21243
Measurements of Time-Dependent Energy Spectra of Beta Rays from Uranium-235 Fission Fragments
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 42-53
Technical Paper / dx.doi.org/10.13182/NSE71-A21244
The Average Number of Neutrons Emitted in the Spontaneous Fission of Some Even-Even Heavy Nuclides
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 54-57
Technical Paper / dx.doi.org/10.13182/NSE71-A21245
Total Neutron Cross Section and Resonance Parameters of Promethium-147
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 58-65
Technical Paper / dx.doi.org/10.13182/NSE71-A21246
Phase-Space Reduction in Neutron Diffusion Calculations
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 66-73
Technical Paper / dx.doi.org/10.13182/NSE71-A21247
Multiple Weighting Functions in Fast Reactor Space-Energy Synthesis
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 74-86
Technical Paper / dx.doi.org/10.13182/NSE71-A21248
Pressure Distribution for Axisymmetric Two-Dimensional Flow in a Plenum During Coolant Expulsion
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 87-90
Technical Note / dx.doi.org/10.13182/NSE71-A21249
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 90-104
Technical Note / dx.doi.org/10.13182/NSE71-A21250
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 105-106
Technical Note / dx.doi.org/10.13182/NSE71-A21251
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 106-108
Technical Note / dx.doi.org/10.13182/NSE71-A21252
Reduction of the Ray Effect in Discrete Ordinates Calculations
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 108-114
Technical Note / dx.doi.org/10.13182/NSE71-A21253
Determining Collision Variances from Adjoints
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 114-116
Technical Note / dx.doi.org/10.13182/NSE71-A21254
Coarse Mesh Acceleration of Iterative Solution of Neutron Diffusion Equation
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 116-120
Technical Note / dx.doi.org/10.13182/NSE71-A21255
Thermal Neutron Diffusion at the Ice-Water Phase Transition
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 120-122
Technical Note / dx.doi.org/10.13182/NSE71-A21256
Consistent Criticality Estimates in Pulsed Neutron Experiments
Nuclear Science and Engineering / Volume 43 / Number 1 / January 1971 / Pages 122-124
Technical Note / dx.doi.org/10.13182/NSE71-A21257
Number 2
Variational Derivation of Discrete Ordinate-Like Approximations
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 131-144
Technical Paper / dx.doi.org/10.13182/NSE71-A21261
Energy-Dependent Neutron Transport Theory in Adjacent Half-Spaces
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 145-153
Technical Paper / dx.doi.org/10.13182/NSE71-A21262
Relationships Between Various Definitions of Prompt-Neutron Lifetime
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 154-158
Technical Paper / dx.doi.org/10.13182/NSE71-A21263
Successive Space-Energy Synthesis for Neutron Fluxes in Fast Reactors
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 159-172
Technical Paper / dx.doi.org/10.13182/NSE71-A21264
Effect of Collapsing Cross-Section Data on Fast Breeder Physics Parameters
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 173-185
Technical Paper / dx.doi.org/10.13182/NSE71-A21265
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 186-196
Technical Paper / dx.doi.org/10.13182/NSE71-A21266
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 197-211
Technical Paper / dx.doi.org/10.13182/NSE71-A21267
Initial Size Distributions of Aerosols
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 212-217
Technical Paper / dx.doi.org/10.13182/NSE71-A21268
Stable Numerical Integration of Conservation Equations for Hydraulic Networks
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 218-225
Technical Paper / dx.doi.org/10.13182/NSE71-A21269
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 226-227
Technical Note / dx.doi.org/10.13182/NSE71-A21270
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 227-229
Technical Note / dx.doi.org/10.13182/NSE71-A21271
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 229-233
Technical Note / dx.doi.org/10.13182/NSE71-A21272
Titanium (n, p) Cross-Section Measurements
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 233-235
Technical Note / dx.doi.org/10.13182/NSE71-A21273
Multigroup Elastic Scattering Cross Sections for Heavy Elements
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 235-237
Technical Note / dx.doi.org/10.13182/NSE71-A21274
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 237-239
Technical Note / dx.doi.org/10.13182/NSE71-A21275
Expected Number of Subassembly Failures Due to Hot Spot Occurrences
Nuclear Science and Engineering / Volume 43 / Number 2 / February 1971 / Pages 239-240
Technical Note / dx.doi.org/10.13182/NSE71-A21276
Number 3
Heat Transfer to a Bingham Plastic in the Entrance Region of a Circular Tube
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 241-246
Technical Paper / dx.doi.org/10.13182/NSE71-A19969
Dispersion of Radioactivity in a Closed Coolant System
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 247-256
Technical Paper / dx.doi.org/10.13182/NSE71-A19970
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 257-266
Technical Paper / dx.doi.org/10.13182/NSE71-A19971
Absolute Gamma-Ray Intensity Measurements of a SNAP-15A Heat Source
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 267-272
Technical Paper / dx.doi.org/10.13182/NSE71-A19972
Differential Measurements of Fast-Neutron Air-Ground Interface Effects
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 273-280
Technical Paper / dx.doi.org/10.13182/NSE71-A19973
High Resolution Fission Cross Section of Uranium-235 from 20 eV to 100 keV
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 281-285
Technical Paper / dx.doi.org/10.13182/NSE71-A19974
Analysis of Exponential Experiments with Lattices of Plutonium in Heavy Water
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 286-302
Technical Paper / dx.doi.org/10.13182/NSE71-A19975
Neutron-Pulse Propagation in Multiplying Assemblies
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 303-314
Technical Paper / dx.doi.org/10.13182/NSE71-A19976
A New Variational Method for the Pulsed-Neutron Problem
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 315-318
Technical Paper / dx.doi.org/10.13182/NSE71-A19977
A Temperature Formulation of the Space-Averaged Reactor Kinetics Equations
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 319-327
Technical Paper / dx.doi.org/10.13182/NSE71-A19978
Energy Modal Synthesis Method in Fast Reactor Analysis
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 328-340
Technical Paper / dx.doi.org/10.13182/NSE71-A19979
The Low-Energy Total Neutron Cross Section of Plutonium-242
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 341-342
Technical Note / dx.doi.org/10.13182/NSE71-A19980
Optimum Refueling Order for Minimum Local Power Peaking Factor
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 342-345
Technical Note / dx.doi.org/10.13182/NSE71-A19981
A Reformulation of the Reactor Kinetics Equations
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 345-348
Technical Note / dx.doi.org/10.13182/NSE71-A19982
Note on Particular Solutions of the Transport Equation
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 348-349
Technical Note / dx.doi.org/10.13182/NSE71-A19983
A Comparison of Federighi's with Marshak's Boundary Conditions
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 349-350
Technical Note / dx.doi.org/10.13182/NSE71-A19984
Escape Probability for Cylinders
Nuclear Science and Engineering / Volume 43 / Number 3 / March 1971 / Pages 350-352
Technical Note / dx.doi.org/10.13182/NSE71-A19985
