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Drop Extraction Between Liquid Metals and Fused Salts
Donald R. Olander
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE68-A18003
Experimental Studies of Microparameters of Clusters of Seven Nuclear Superheat Reactor Fuel Rods
J. T. Wajima, H. Yamamoto, H. Kikuchi, T. Ohnishi, S. Kobayashi
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 19-31
Technical Paper | doi.org/10.13182/NSE68-A18004
Theoretical Analyses of Homogeneous Plutonium Critical Experiments
C. R. Richey
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 32-39
Technical Paper | doi.org/10.13182/NSE68-A18005
Criticality of Heterogeneous Arrays Undergoing Dissolution
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 40-48
Technical Paper | doi.org/10.13182/NSE68-A18006
Age Measurements in ThO2-D2O-H2O Lattices
Donald M. Roberts, William G. Pettus
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 49-56
Technical Paper | doi.org/10.13182/NSE68-A18007
A Comparison of Heterogeneous Nuclear-Reactor Lattice Theory with Experiment
W. E. Graves, F. D. Benton, R. M. Satterfield
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 57-66
Technical Paper | doi.org/10.13182/NSE68-A18008
On the Stability of Nonlinear Space-Dependent Reactor Kinetics
William E. Kastenberg, Paul L. Chambré
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 67-79
Technical Paper | doi.org/10.13182/NSE68-A18009
On the Use of Dual Variational Principles for the Estimation of Error in Approximate Solutions of Diffusion Problems
J. B. Yasinsky, S. Kaplan
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 80-90
Technical Paper | doi.org/10.13182/NSE68-A18010
Flux Synthesis Using Green's Function in Two-Dimensional Group Diffusion Equations
Keisuke Kobayashi
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 91-101
Technical Paper | doi.org/10.13182/NSE68-A18011
Neutron Thermalization in Heavy Gas with Nonuniform Temperature Distribution
Pekka Jauho, Antti Virjo
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 102-109
Technical Paper | doi.org/10.13182/NSE68-A18012
Albedo and Milne's Problem for Thermal Neutrons
S. Pahor
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 110-116
Technical Paper | doi.org/10.13182/NSE68-A18013
A Boltzmann Integral Equation Treatment of Neutron Resonance Absorption in Reactor Lattices
E. E. Lewis, F. T. Adler
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 117-126
Technical Paper | doi.org/10.13182/NSE68-A18014
Transport Error Bounds Via PN Approximations
James A. Davis
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 127-146
Technical Paper | doi.org/10.13182/NSE68-A18015
A Study Concerning the Number of “Effective” Equally Limiting Hot Channels in a Reactor with a Cosine Power Distribution
F. D. Judge
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 147-148
Technical Note | doi.org/10.13182/NSE68-A18016
Effects of Voids on Diffusion Length and Streaming of Neutrons in Water
Naeem Ahmad Khan, S. M. Kabir
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 148-149
Technical Note | doi.org/10.13182/NSE68-A18017
Neutron Absorption Cross Section of 237U
W. R. Cornman, E. J. Hennelly, C. J. Banick
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 149-152
Technical Note | doi.org/10.13182/NSE68-A18018
The Thermal-Neutron Capture Cross Section of Cadmium
J. W. Meadows
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 152-153
Technical Note | doi.org/10.13182/NSE68-A18019
Neutron Spectra in Thin Polyethylene Slabs
S. B. Armstrong
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 153-155
Technical Note | doi.org/10.13182/NSE68-A18020
Neglect of the Energy-Angle Correlation in Nonscattering Neutron Emission Reactions
S. T. Perkins
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 156-157
Technical Note | doi.org/10.13182/NSE68-A18021
On Solving Certain Group-Diffusion Problems in Finite-Difference Form
Melvin Tobias
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 157-160
Technical Note | doi.org/10.13182/NSE68-A18022
Time-Dependent Variational Theory
Jeffery Lewins
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 160-163
Technical Note | doi.org/10.13182/NSE68-A18023
The Effect of Source Distribution on Neutron Resonance Integrals
A. C. deLoach and J. E. Suich
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 163-167
Technical Note | doi.org/10.13182/NSE68-A18024
A Reformulation of the Doppler Effect in Resonant Neutron Capture
W. G. Pettus
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 168-169
Technical Note | doi.org/10.13182/NSE68-A18025
Study of Lithium Mobility in Irradiated Silicon
Walter A. Hackler, Chihiro Kikuchi
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 175-182
Technical Paper | doi.org/10.13182/NSE68-A18229
Geometry and Barrier Attenuation of Cobalt-60 Gamma Rays by a Vertical Steel Slab
G. E. Plummer
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 183-190
Technical Paper | doi.org/10.13182/NSE68-A18230
A Study of Fission-Neutron Spectra with High-Energy Activation Detectors. Part II: Fission Spectra
James A. Grundl
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 191-206
Technical Paper | doi.org/10.13182/NSE68-A18231
The Energy Spectrum of Fast Neutrons Slowing Down from a Fission Source in a Homogeneous Medium
T. E. Murley, I. Kaplan
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 207-214
Technical Paper | doi.org/10.13182/NSE68-A18232
Cross-Spectral Density Measurements in a Coupled-Core Reactor
Richard A. Hendrickson, Glenn Murphy
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 215-221
Technical Paper | doi.org/10.13182/NSE68-A18233
Analysis of Pulsed Fast-Neutron Spectra in Multiplying Assemblies
J. D. Jenkins, P. B. Daitch
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 222-233
Technical Paper | doi.org/10.13182/NSE68-A18234
The Statistical Estimation of Thermal-Neutron Cross Sections
J. L. Cook, A. L. Wall
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 234-240
Technical Paper | doi.org/10.13182/NSE68-A18235
Measurement of 135I Yield Ratios and Fission-Product Cross Sections in the Advanced Reactivity Measurement Facilities
R. G. Nisle, I. E. Stepan
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 241-246
Technical Paper | doi.org/10.13182/NSE68-A18236
Low-Flux Measurement of 235U Epicadmium Capture-to-Fission Ratio
W. C. Redman, M. M. Bretscher
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 247-253
Technical Paper | doi.org/10.13182/NSE68-A18237
Neutron Scattering from Light Water
J. R. Beyster
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 254-271
Technical Paper | doi.org/10.13182/NSE68-A18238
Energy Optimal Xenon Shutdown
Jeffrey Lewins, Gordon R. Woodcock, Theodore J. Williamson, Albert L. Babb
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 272-281
Technical Paper | doi.org/10.13182/NSE68-A18239
Monte Carlo Analysis of Nuclear Reactor Fluctuation Models
Burt A. Zolotar
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 282-294
Technical Paper | doi.org/10.13182/NSE68-A18240
Monoenergetic Critical Parameters and Decay Constants for Small Homogeneous Spheres and Thin Homogeneous Slabs
I. Carlvik
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 295-303
Technical Paper | doi.org/10.13182/NSE31-295
Numerical Solution of the Time-Dependent Multigroup Diffusion Equations
J. Barclay Andrews, II, K. F. Hansen
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 304-313
Technical Paper | doi.org/10.13182/NSE68-A18242
Comparison of Neutron-Transport and Diffusion Theories of Isotropic Scattering
P. S. Grover, L. S. Kothari, A. K. Ghatak
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 314-317
Technical Paper | doi.org/10.13182/NSE68-A18243
Accuracy of Transport Theory Calculations of an Anisotropic Neutron Flux
Pekka Jauho, Heikki Kalli
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 318-324
Technical Paper | doi.org/10.13182/NSE68-A18244
A Strategy for the Application of Space-Angle Synthesis to Practical Problems in Neutron Transport
M. Natelson
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 325-336
Technical Paper | doi.org/10.13182/NSE68-A18245
Effect of Property Variation on the Turbulent Flow of Gases in Tubes: The Thermal Entry
P. M. Magee, D. M. McEligot
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 337-341
Technical Note | doi.org/10.13182/NSE68-A18246
Total Cross Sections of Na, K, and Ca for 14-MeV Neutrons
F. Guarrini, A. Luches, G. Pauli, G. Poiani
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 341-343
Technical Note | doi.org/10.13182/NSE68-A18247
Absolute Neutron Yields from Thick Target NATC(α,n)
R. L. Macklin, J. H. Gibbons
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Page 343
Technical Note | doi.org/10.13182/NSE68-A18248
Comparison of Beryllium Photoneutron Decay Sets Using Experimental SNAP Data
Eric H. Ottewitte
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 343-346
Technical Note | doi.org/10.13182/NSE68-A18249
Suggested Procedures for Utilizing MUFT Resonance Parameters to Include Doppler Broadening
David T. Goldman
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 346-349
Technical Note | doi.org/10.13182/NSE68-A18250
The Application of Synthesis Techniques to the Calculations of Three-Dimensional Reactivity-Coefficient Distributions
J. L. Bear, F. D. Judge, E. R. Venerus
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 349-353
Technical Note | doi.org/10.13182/NSE68-A18251
Anomalies Arising from the Use of Adjoint Weighting in a Collapsed Group-Space Synthesis Model
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 354-358
Technical Note | doi.org/10.13182/NSE68-A18252
Flux Tilting in a Two-Zone Reactor
D. E. Jeffers, K. Hall
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 358-359
Technical Note | doi.org/10.13182/NSE68-A18253
S∞ Neutron Transport Theory in Plane Geometry
J. Mennig, J. T. Marti
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 365-368
Technical Paper | doi.org/10.13182/NSE68-A17580
An Improved Method for Calculating Rethermalization Neutron Cross Sections
Roger W. Carlson and K. F. Hansen
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 369-376
Technical Paper | doi.org/10.13182/NSE68-A17581
An Activation Experiment to Determine the Coefficients in the Laguerre Expansion of Perturbed Thermal-Neutron Spectra
Jacek Jedruch
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 377-387
Technical Paper | doi.org/10.13182/NSE68-A17582
Intermediate Neutron Resonance Absorption in Heterogeneous Systems
Yukio Ishiguro and Hideki Takano
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 388-395
Technical Paper | doi.org/10.13182/NSE68-A17583
Adjusting Absorption Cross Sections in Transport Calculations to Achieve Specified Region Capture Integrals
Donald S. Rampolla
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 396-414
Technical Paper | doi.org/10.13182/NSE68-A17584
Effective Resonance Integrals of Separated Tungsten Isotopes from Reactivity Measurements
Donald F. Shook and Donald Bogart
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 415-430
Technical Paper | doi.org/10.13182/NSE68-A17585
Determination of Dilute 186W and 184W Resonance Integrals by Activation
Clarence R. Pierce and Donald F. Shook
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 431-439
Technical Paper | doi.org/10.13182/NSE68-A17586
Variances and Covariances of Neutron and Precursor Populations in Time-Varying Reactions
W. G. Clarke, D. R. Harris, M. Natelson, J. F. Walter
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 440-457
Technical Paper | doi.org/10.13182/NSE68-A17587
A Generalized Formulation of Point Nuclear Reactor Kinetics Equations
Martin Becker
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 458-464
Technical Paper | doi.org/10.13182/NSE68-A17588
On Transient Digital Control of Large Nuclear Power Reactors
W. Ciechanowicz
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 465-473
Technical Paper | doi.org/10.13182/NSE68-A17589
On the On-Line Statistical Identification of Nuclear Power Reactor Dynamics
W. Ciechanowicz and S. Bogumil
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 474-483
Technical Paper | doi.org/10.13182/NSE68-A17590
Neutron-Wave Propagation Through a Crystalline Moderator-I: Beryllium
Feroz Ahmed, P. S. Grover, L. S. Kothari
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 484-491
Technical Paper | doi.org/10.13182/NSE68-A17591
The Application of Track-Length Distribution Biasing in Monte Carlo Deep-Penetration Calculations
R. H. Karcher, R. C. Erdmann, O. C. Baldonado
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 492-499
Technical Paper | doi.org/10.13182/NSE68-A17592
The Use of Self-Optimized Exponential Biasing in Obtaining Monte Carlo Estimates of Transmission Probabilities
Leo B. Levitt
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 500-504
Technical Paper | doi.org/10.13182/NSE68-A17593
The Synthesis Method of Uncertainty Analysis in Nuclear Reactor Thermal Design
Henri Fenech and Henri M. Guéron
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 505-512
Technical Paper | doi.org/10.13182/NSE68-A17594
Thermal-Neutron-Induced Defects in n-Type Cadmium Telluride
Charles Barnes and Chihiro Kikuchi
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 513-520
Technical Paper | doi.org/10.13182/NSE68-A17595
Reactor Organic Coolants III: Temperature, Intensity and Post irradiation Effects in the Electron Radiolysis of Meta-Terphenyl
Donna Wuschke and M. Tomlinson
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 521-530
Technical Paper | doi.org/10.13182/NSE68-A17596
On the Dispersion of Fission Products from Laminar Streams in Open- and Closed-Loop Conduits
E. R. Venerus and M. N. Ozisik
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 531-539
Technical Paper | doi.org/10.13182/NSE68-A17597
An Iterative Method for Determination of a Minimal Eigenvalue
G. K. Kristiansen
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Page 540
Technical Note | doi.org/10.13182/NSE68-A17598
The Temperature Dependence of the Effective Resonance Integral of Thorium Oxide Rods
J. A. Kadlecek, F. C. Schoenig, K. S. Quisenberry
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 541-544
Technical Note | doi.org/10.13182/NSE68-A17599
Reactor Neutron Cross Sections for Some (n, γ) Reactions
R. S. Tilbury and Henry H. Kramer
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 545-546
Technical Note | doi.org/10.13182/NSE68-A17600
Time-of-Flight Effects in Pulsed-Neutron Measurements
Glenn A. Price and Henry H. Windsor
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 547-548
Technical Note | doi.org/10.13182/NSE68-A17601
Low-Enrichment Uranium-Metal Exponential Experiments
C. G. Chezem and R. G. Steinke
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Page 549
Technical Note | doi.org/10.13182/NSE68-A17602
Acceleration of the Convergence of Successive Block Overrelaxation by Use of an Improved Block Pattern in the Solution of the Equation for Transient Heat Conduction
B. Kaplan and K. D. Wright
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Page 550
Technical Note | doi.org/10.13182/NSE68-A17603
Metal-Water Explosions
Fredrick E. Brauer, N. Wayne Green, Russell B. Mesler
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 551-554
Technical Note | doi.org/10.13182/NSE68-A17604