Volume 41
Number 1 | Number 2 | Number 3
Number 1
Burnup Optimization of Continuous Scattered Refueling
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 1-13
Technical Paper / dx.doi.org/10.13182/NSE70-A20357
A Numerical Method for the Solution of Three-Dimensional Neutron-Transport Problems
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 14-21
Technical Paper / dx.doi.org/10.13182/NSE70-A20358
Extrapolation Distances and Diffusion Parameters via Pulsed-Neutron Analysis
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 22-28
Technical Paper / dx.doi.org/10.13182/NSE70-A20359
An Analytic Representation of Fast-Reactor Neutron-Energy Spectra
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 29-36
Technical Paper / dx.doi.org/10.13182/NSE70-A20360
Estimation of Spatial Distributions of Neutron Captures in Resonance Absorbers
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 37-46
Technical Paper / dx.doi.org/10.13182/NSE70-A20361
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 47-55
Technical Paper / dx.doi.org/10.13182/NSE70-A20362
A Measurement of the Capture-to-Fission Ratio for Plutonium-239
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 56-62
Technical Paper / dx.doi.org/10.13182/NSE70-A20363
Fast-Neutron Total and Scattering Cross Sections of Bismuth
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 63-69
Technical Paper / dx.doi.org/10.13182/NSE70-A20364
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 70-78
Technical Paper / dx.doi.org/10.13182/NSE70-A20365
Two-Phase Critical Flow at Low Qualities Part I: Experimental
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 79-91
Technical Paper / dx.doi.org/10.13182/NSE70-A20366
Two-Phase Critical Flow at Low Qualities Part II: Analysis
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 92-98
Technical Paper / dx.doi.org/10.13182/NSE70-A20367
Theoretical Investigations on Sodium Boiling in Fast Reactors
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 99-114
Technical Paper / dx.doi.org/10.13182/NSE70-A20368
Space-Dependent Dynamic Behavior of Fast Reactors Using the Time-Discontinuous Synthesis Method
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 115-125
Technical Note / dx.doi.org/10.13182/NSE70-A20369
State Variable Feedback and Series Compensation of Multivariate Systems
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 125-129
Technical Note / dx.doi.org/10.13182/NSE70-A20370
Stochastic Stability of a Reactor with Linear Feedback
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 129-132
Technical Note / dx.doi.org/10.13182/NSE70-A20371
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 132-138
Technical Note / dx.doi.org/10.13182/NSE70-A20372
Pulse Neutron Decay in Heavy-Water Spheres
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 138-140
Technical Note / dx.doi.org/10.13182/NSE70-A20373
Legendre Moments of the Elastic-Scattering Cross Section for S-Wave Neutrons
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 140-143
Technical Note / dx.doi.org/10.13182/NSE70-A20374
Derivation of 239Pu Resonance Parameters from Correlation of Experimental Data
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 143-146
Technical Note / dx.doi.org/10.13182/NSE70-A20375
Effective Capture and Fission Cross Sections for Californium-253
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 146-147
Technical Note / dx.doi.org/10.13182/NSE70-A20376
Nuclear Science and Engineering / Volume 41 / Number 1 / July 1970 / Pages 147-148
Technical Note / dx.doi.org/10.13182/NSE70-A20377
Number 2
Primary-Recoil Atom Spectra from ENDF/B Data
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 155-163
Technical Paper / dx.doi.org/10.13182/NSE70-A20703
Neutron Spectrum Measurements in a Homogeneous Erbium System and Erbium Cross Sections
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 164-176
Technical Paper / dx.doi.org/10.13182/NSE70-A20704
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 177-187
Technical Paper / dx.doi.org/10.13182/NSE70-A20705
Total Neutron Cross Section of Technetium-99 from 0.01 to 1000 eV
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 188-192
Technical Paper / dx.doi.org/10.13182/NSE70-A20706
A Unified Model of Deformed Odd-Odd Nuclei for Nuclear Data Generation and Analysis
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 193-208
Technical Paper / dx.doi.org/10.13182/NSE70-A20707
Reaction Rates in Representative Plutonium-Recycle Fuel Lattices
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 209-225
Technical Paper / dx.doi.org/10.13182/NSE70-A20708
Linearly Anisotropic Extensions of Asymptotic Neutron Diffusion Theory
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 226-236
Technical Paper / dx.doi.org/10.13182/NSE70-A20709
Truncation Error Analysis of Finite Difference Approximations to the Transport Equation
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 237-248
Technical Paper / dx.doi.org/10.13182/NSE70-A20710
Spectral Synthesis Applied to Fast-Reactor Dynamics
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 249-258
Technical Paper / dx.doi.org/10.13182/NSE70-A20711
Monte Carlo Method for Geometrical Perturbation and its Application to the Pulsed Fast Reactor
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 259-270
Technical Paper / dx.doi.org/10.13182/NSE70-A20712
Hybrid Computer Solution of Thermal Energy Equations in Porous Fuels
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 271-280
Technical Paper / dx.doi.org/10.13182/NSE70-A20713
Transient Digital Control of a Boiling-Water Reactor Power Plant
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 281-293
Technical Paper / dx.doi.org/10.13182/NSE70-A20714
An Experimental Investigation of Absorption in the 1.056 eV Resonance of Plutonium-240
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 294-296
Technical Note / dx.doi.org/10.13182/NSE70-A20715
Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt Neutron Decay Measurements
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 296-298
Technical Note / dx.doi.org/10.13182/NSE70-A20716
Gozani's Pulsed Neutron Technique with Repeated Recycling of Analyzer Between Bursts
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 298-299
Technical Note / dx.doi.org/10.13182/NSE70-A20717
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 299-303
Technical Note / dx.doi.org/10.13182/NSE70-A20718
Interface Conditions for Discontinuous Flux Synthesis Methods
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 303-307
Technical Note / dx.doi.org/10.13182/NSE70-A20719
A Slow Neutron Scattering Routine from the Gas Model
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 307-309
Technical Note / dx.doi.org/10.13182/NSE70-A20720
Geometric Interpretation of the Function g(c,µ) of Neutron Transport Theory
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 309-310
Technical Note / dx.doi.org/10.13182/NSE70-A20721
Comparisons of Monte Carlo Calculations to Measurements of Neutron Leakage from the TSF-SNAP Reactor
Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 310-315
Technical Note / dx.doi.org/10.13182/NSE70-A20722
Number 3
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 321-335
Technical Paper / dx.doi.org/10.13182/NSE70-A19090
The Two-Phase Critical Discharge of Initially Saturated or Subcooled Liquid
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 336-342
Technical Paper / dx.doi.org/10.13182/NSE70-A19091
Statistical Evaluation of the Maximum Temperatures in Reactor Cores
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 343-350
Technical Paper / dx.doi.org/10.13182/NSE70-A19092
The Total Neutron Cross Section of Lithium-7 and Carbon from 100 to 1500 keV
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 351-356
Technical Paper / dx.doi.org/10.13182/NSE70-A19093
Measurements of Thermal Neutron Spectra in Heterogeneous Lattices by Foil Activation
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 357-366
Technical Paper / dx.doi.org/10.13182/NSE70-A19094
Comparison of Calculated and Measured Energy-Dependent Activation Rates for NERVA-Type Reactor
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 367-380
Technical Paper / dx.doi.org/10.13182/NSE70-A19095
Continuous Slowing Down Theory Applied to Fast-Reactor Assemblies
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 381-393
Technical Paper / dx.doi.org/10.13182/NSE70-A19096
An Exact Solution of The Neutron Slowing Down Equation
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 394-398
Technical Paper / dx.doi.org/10.13182/NSE70-A19097
Higher Order Variational Principles and Iterative Processes
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 399-403
Technical Paper / dx.doi.org/10.13182/NSE70-A19098
Time-Dependent Neutron Transport Theory for Fast Pulsed Assemblies
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 404-416
Technical Paper / dx.doi.org/10.13182/NSE70-A19099
The Information in Neutron Fluctuations
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 417-430
Technical Paper / dx.doi.org/10.13182/NSE70-A19100
Alternating Direction Methods for the Reactor Kinetics Equations
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 431-442
Technical Paper / dx.doi.org/10.13182/NSE41-431
Characterization of Porous Media in Terms of Their Gas Transmission Properties
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 443-445
Technical Note / dx.doi.org/10.13182/NSE70-A19102
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 445-449
Technical Note / dx.doi.org/10.13182/NSE70-A19103
Calculated Activation of Copper and Iron by 3-GeV Protons
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 449-451
Technical Note / dx.doi.org/10.13182/NSE70-A19104
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 452-455
Technical Note / dx.doi.org/10.13182/NSE70-A19105
Resolved Narrow Resonance Reaction Rates in Fast-Reactor Mixtures
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 455-457
Technical Note / dx.doi.org/10.13182/NSE70-A19106
Nuclear Science and Engineering / Volume 41 / Number 3 / September 1970 / Pages 457-461
Technical Note / dx.doi.org/10.13182/NSE70-A19107
