Volume 47
Number 1
- Table of Contents
- REPP
- QX1: A One-Dimensional Multigroup Kinetics Program
- SN35
- APEL
- “On the Use of Acoustic Waves in Nuclear Power Reactors to Determine Average Void Fractions”
- “A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations”
- “The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons”
- “Matrix Riemann-Hilbert Problems Related to Neutron Transport Theory”
Gamma-Ray Albedo Calculations Using Moments Method
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 1-7
Technical paper / dx.doi.org/10.13182/NSE72-A28415
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 8-18
Technical paper / dx.doi.org/10.13182/NSE72-A28416
Fast Neutron Total and Scattering Cross Sections of Plutonium-240
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 19-28
Technical paper / dx.doi.org/10.13182/NSE72-A28417
The Effect of Wide Scattering Resonances on Neutron Multigroup Cross Sections
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 29-39
Technical paper / dx.doi.org/10.13182/NSE72-A28418
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 40-58
Technical paper / dx.doi.org/10.13182/NSE72-A28419
Benchmark Gas Core Critical Experiment
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 59-65
Technical paper / dx.doi.org/10.13182/NSE72-A28420
Improvements to Neutron Slowing Down Theory for Fast Reactors
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 66-82
Technical paper / dx.doi.org/10.13182/NSE72-A28421
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 83-103
Technical paper / dx.doi.org/10.13182/NSE72-A28422
The Concept of Multiple-Input Zero Power Describing Functions in Nuclear Reactors
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 104-115
Technical paper / dx.doi.org/10.13182/NSE72-A28423
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 116-126
Technical paper / dx.doi.org/10.13182/NSE72-A28424
Safety Effects of Light Water Infiltration in the Argonne Research Reactor (CP-5)
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 127-131
Technical paper / dx.doi.org/10.13182/NSE72-A28425
Physical Properties of the“Once Through Then Out” Pebble-Bed Reactor
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 132-139
Technical paper / dx.doi.org/10.13182/NSE72-A28426
The Hot Channel Factor as Determined by the Permissible Number of Hot Channels in the Core
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 140-149
Technical paper / dx.doi.org/10.13182/NSE72-A28427
A Dead Time Correction for Gamma-Ray Spectroscopy
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 150-151
Technical Note / dx.doi.org/10.13182/NSE72-A28428
The Thermal-Neutron Capture Cross Section and Resonance Capture Integral of Krypton-80
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 151-153
Technical Note / dx.doi.org/10.13182/NSE72-A28429
Steady-State Neutron Spectra in Ice in the Temperature Range 268 to 4°K
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 153-156
Technical Note / dx.doi.org/10.13182/NSE72-A28430
Two-Group Neutron Transport Theory with Anisotropic Scattering
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 156-162
Technical Note / dx.doi.org/10.13182/NSE72-A28431
MOD-5 A Discrete Markov Slowing Down Code
Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Page 164
Computer Code Abstract / dx.doi.org/10.13182/NSE72-A28433
