Volume 86
Number 1 | Number 2 | Number 3 | Number 4
Number 1
- Table of Contents
- Comment on “Reduction of ‘Calculational’ Uncertainties Due to Approximate Fission-Source Matrices”
- Reply to “Comment on ‘Reduction of “Calculational” Uncertainties Due to Approximate Fission-Source Matrices’”
- Propagation of Knowledge Regarding Conservation During Doppler Broadening
- Responses to “Propagation of Knowledge Regarding Conservation During Doppler Broadening”
- Comment on “Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters”
- Response to “Comment on ‘Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters’”
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 1-9
Technical Paper / dx.doi.org/10.13182/NSE84-A17965
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 10-21
Technical Paper / dx.doi.org/10.13182/NSE84-A17966
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 22-40
Technical Paper / dx.doi.org/10.13182/NSE84-A17967
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 41-46
Technical Paper / dx.doi.org/10.13182/NSE84-A17968
Scattering Anisotropy and Neutron Leakage in Reactor Lattices
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 47-62
Technical Paper / dx.doi.org/10.13182/NSE84-A17969
A Spherical Harmonics Method Utilizing Polynomials Which Are Both Angularly and Spatially Dependent
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 63-75
Technical Paper / dx.doi.org/10.13182/NSE84-A17970
Internal Interface Perturbations in Neutron Transport Theory
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 76-90
Technical Paper / dx.doi.org/10.13182/NSE84-A17971
Space-Time Analysis of Reactor-Control-Rod-Worth Measurements
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 91-105
Technical Paper / dx.doi.org/10.13182/NSE84-1
Neutron Yields from Uranium-Fluorine Compounds
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 106-109
Technical Note / dx.doi.org/10.13182/NSE84-A17973
Dancoff's Solution for the Number of Collisions Necessary to Slow Down
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 110-111
Technical Note / dx.doi.org/10.13182/NSE84-A17974
Bayesian Estimation of Core-Melt Probability
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 111-112
Technical Note / dx.doi.org/10.13182/NSE84-A17975
Utilization of Thorium in Light Water Reactors
Nuclear Science and Engineering / Volume 86 / Number 1 / January 1984 / Pages 112-115
Technical Note / dx.doi.org/10.13182/NSE84-A17976
Number 2
- Table of Contents
- Nuclear Reactor Safety: On the History of the Regulatory Process
- Glossary of Terms in Heat Transfer: Fluid Flow, and Related Topics
- Effects of Phase and Velocity Distribution on Two-Phase Pressure Pulse Propagation
- Reply to “Effects of Phase and Velocity Distribution on Two-Phase Pressure Pulse Propagation”
Multinode Reactor Stability and Optimal Estimates of Domains of Attraction
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 129-135
Technical Paper / dx.doi.org/10.13182/NSE84-A18195
Subcritical Problems in Spherical Geometry
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 136-149
Technical Paper / dx.doi.org/10.13182/NSE86-136
Critical Problems for Bare and Reflected Slabs and Spheres
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 150-156
Technical Paper / dx.doi.org/10.13182/NSE86-150
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 157-167
Technical Paper / dx.doi.org/10.13182/NSE84-A18198
Neutron Capture in s-Wave Resonances of Iron-56, Nickel-58, and Nickel-60
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 168-183
Technical Paper / dx.doi.org/10.13182/NSE84-A18199
Measurements of Differential 14.7-MeV Neutron Scattering Cross Sections of Lithium-7 and Beryllium-9
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 184-190
Technical Paper / dx.doi.org/10.13182/NSE84-A18200
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 191-205
Technical Paper / dx.doi.org/10.13182/NSE84-A18201
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 206-218
Technical Paper / dx.doi.org/10.13182/NSE84-2
Calculations of the Spectra of Fast Neutrons in Iron Spheres Using the Vitamin-C File
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 219-224
Technical Note / dx.doi.org/10.13182/NSE84-A18203
Comparison of Some Finite Difference Formulas for Use with Equilateral Triangular Mesh Grid SN Codes
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 224-228
Technical Note / dx.doi.org/10.13182/NSE84-A18204
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 229-231
Technical Note / dx.doi.org/10.13182/NSE84-A18205
Compatibility Tests of Low-Vapor Pressure Perfluoropolyether Oils with UF6
Nuclear Science and Engineering / Volume 86 / Number 2 / February 1984 / Pages 232-238
Technical Note / dx.doi.org/10.13182/NSE84-A18206
Number 3
Equilibrium Relationships in the Uranium-Manganese-Oxygen System in Air
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 247-252
Technical Paper / dx.doi.org/10.13182/NSE84-A17553
A Model for the Thermal-Mechanical Behavior of Mixed-Carbide Sphere-Pac Fuel Pins
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 253-266
Technical Paper / dx.doi.org/10.13182/NSE84-A17554
The Transport of Heavy Charged Particles in a Cylindrical Nuclear-Pumped Plasma
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 267-274
Technical Paper / dx.doi.org/10.13182/NSE84-A17555
Decision Procedures for Material Balance Sequences
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 275-282
Technical Paper / dx.doi.org/10.13182/NSE84-A17556
Stability Region for a Prompt Power Variation of a Coupled-Core System with Positive Prompt Feedback
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 283-296
Technical Paper / dx.doi.org/10.13182/NSE84-A17557
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 297-301
Technical Paper / dx.doi.org/10.13182/NSE84-A17558
Response Matrix of Symmetric Nodes
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 302-314
Technical Paper / dx.doi.org/10.13182/NSE84-A17559
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 315-319
Technical Note / dx.doi.org/10.13182/NSE84-A17560
Macro- and Microflux, I: Periodic Lattices
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 319-326
Technical Note / dx.doi.org/10.13182/NSE84-A17561
Nuclear Science and Engineering / Volume 86 / Number 3 / March 1984 / Pages 326-331
Technical Note / dx.doi.org/10.13182/NSE84-A17562
Number 4
Flux-Limited Diffusion Theory with Anisotropic Scattering
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 335-343
Technical Paper / dx.doi.org/10.13182/NSE84-A18634
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 344-354
Technical Paper / dx.doi.org/10.13182/NSE84-A18635
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 355-361
Technical Paper / dx.doi.org/10.13182/NSE84-A18636
Neutron Capture Cross Sections of Tantalum from 2.6 to 1900 keV
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 362-371
Technical Paper / dx.doi.org/10.13182/NSE84-A18637
Molten Fuel/Coolant Interactions: Recent Analysis of Experiments
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 372-387
Technical Paper / dx.doi.org/10.13182/NSE84-A18638
A Practical Nonhomogeneous Two-Phase Flow Model for Light Water Reactor System Codes
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 388-400
Technical Paper / dx.doi.org/10.13182/NSE84-A18639
Universality and Aperiodic Behavior of Nuclear Reactors
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 401-404
Technical Note / dx.doi.org/10.13182/NSE84-A18640
Precursors in Bayesian Estimation of Core-Melt Probability
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 404-405
Technical Note / dx.doi.org/10.13182/NSE84-A18641
Helical Geometry Effect on Tritium Breeding in Heliotron Fusion Reactor Blanket
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 405-409
Technical Note / dx.doi.org/10.13182/NSE84-A18642
Introduction of Partial Convergence Idea into Void Iteration for Boiling Water Reactor Computations
Nuclear Science and Engineering / Volume 86 / Number 4 / April 1984 / Pages 409-412
Technical Note / dx.doi.org/10.13182/NSE84-A18643
