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Neutron Diffusion Lengths of Graphite-Absorber Mixtures Between 200 and 2000°K
W. W. Clendenin
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE69-A18852
Measurement of Neutron Flux Spectra by a Multiple Foil Activation Iterative Method and Comparison with Reactor Physics Calculations and Spectrometer Measurements
W. N. McElroy, S. Berg, T. B. Crockett, R. J. Tuttle
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 15-27
Technical Paper | doi.org/10.13182/NSE69-A18853
A Space-Dependent Reactor-Noise Formulation Utilizing Modal Expansions
R. A. Danofsky
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 28-38
Technical Paper | doi.org/10.13182/NSE69-A18854
The Bimodal Decay of Two Pulsed-Neutron-Coupled Cores of an Organic-Moderated and -Reflected System
U. Farinelli, N. Pacilio
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 39-46
Technical Paper | doi.org/10.13182/NSE69-A18855
Resonance Integral and Doppler Coefficients in Nonuniform Cylindrical Reactor Fuel Rods
J. J. Van Binnebeek
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 47-58
Technical Paper | doi.org/10.13182/NSE69-A18856
Resonance Moderation of Neutrons in Weakly Absorbing Mixtures
M. Segev
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 59-66
Technical Paper | doi.org/10.13182/NSE69-A18857
Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—I
R. N. Hwang
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 67-81
Technical Paper | doi.org/10.13182/NSE69-A18858
Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—II
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 82-96
Technical Paper | doi.org/10.13182/NSE69-A18859
Comparison of Modal and Iterative Approaches to Space and Space-Time Nonlinear Problems
Louis M. Shotkin
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 97-104
Technical Paper | doi.org/10.13182/NSE69-A18860
Multiple Scattering in Double Differential Measurements as a Function of Neutron Path Length
E. L. Slaggie
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 105-107
Technical Note | doi.org/10.13182/NSE69-A18861
Iteration and Intermediate Resonance Neutron Absorption in Multinuclide Systems
F. de Kruijf
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 107-109
Technical Note | doi.org/10.13182/NSE69-A18862
Implications of Recent Fission-Averaged Cross-Section Measurements
W. N. McElroy
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 109-113
Technical Note | doi.org/10.13182/NSE69-A18863
On the Step-Response Method of Determining the Zero-Power Reactor Transfer Function
D. M. Chapin
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 113-114
Technical Note | doi.org/10.13182/NSE69-A18864
Discrepancy Between Measured and Calculated Reactivity Coefficients in Dilute Plutonium Fueled Fast Criticals
W. W. Little, Jr., R. W. Hardie
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 115-116
Technical Note | doi.org/10.13182/NSE69-A18865
An Evaluation of Homogeneous and Heterogeneous Methods of Analysis in a Reflected Subcritical Assembly
M. R. Haroon
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 116-122
Technical Note | doi.org/10.13182/NSE69-A18866
A Method for Calculating Space-Dependent Reactor Source Transfer Functions with Feedback
D. N. Bridges, J. D. Clement, J. P. Renier
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 122-125
Technical Note | doi.org/10.13182/NSE69-A18867
Reactivity Rate-Constrained Time-Optimal Neutron Kinetics
S. F. Moon, R. R. Mohler
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 125-128
Technical Note | doi.org/10.13182/NSE69-A18868
Time-Energy-Dependent Neutron Transport in an Infinite Medium in the Framework of Age-Dependent Branching Processes
P. Wälti
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 133-142
Technical Paper | doi.org/10.13182/NSE69-A19713
Experimental Neutron Kinetic Studies in a 238U Sphere
Tsahi Gozani
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 143-158
Technical Paper | doi.org/10.13182/NSE69-A19714
The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors
Amir N. Nahavandi
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 159-188
Technical Paper | doi.org/10.13182/NSE69-A19715
A Unified Nuclear Model for the Generation of Nuclear Data
K. J. Yost, P. H. Pitkanen, C. Y. Fu
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 189-201
Technical Paper | doi.org/10.13182/NSE69-A19716
The Measurement of Absolute Delayed-Neutron Yields from 3.1- and 14.9-MeV Fission
Christopher F. Masters, M. M. Thorpe, Darryl B. Smith
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 202-208
Technical Paper | doi.org/10.13182/NSE69-A19717
An Accurate Determination of the Cadmium Ratio of Neutron Capture Rates in 238U in Slightly Enriched Uranium
Ç. Ertek, A. Yalçin, Y. İnel
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 209-219
Technical Paper | doi.org/10.13182/NSE69-A19718
The Application of a Gamma-Ray Cascade Model to the Calculation of Neutron Energy-Dependent Capture Gamma-Ray Production Cross Sections
K. J. Yost, S. M. Kremer
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 220-231
Technical Paper | doi.org/10.13182/NSE69-A19719
Measurements of Nonfission Heating in a High Neutron Flux Reactor
R. M. Carroll, R. B. Perez, O. Sisman
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 232-237
Technical Paper | doi.org/10.13182/NSE69-A19720
Experimental Studies on Gamma-Ray Dose Rates from a 60Co Cylindrical Source with Shell-Shaped Shields
Yoshihiko Kanemori, Yutaka Furuta
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 238-245
Technical Paper | doi.org/10.13182/NSE69-A19721
A Semiempirical Formula for Albedo of Alternating Layers
Takashi Nakamura, Tomonori Hyodo
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 246-250
Technical Paper | doi.org/10.13182/NSE69-A19722
High-Energy (<400-MeV) Neutron Transport Using the Method of Discrete Ordinates
R. G. Alsmiller, Jr., F. R. Mynatt, J. Barish, W. W. Engle, Jr.
Nuclear Science and Engineering | Volume 36 | Number 2 | May 1969 | Pages 251-255
Technical Note | doi.org/10.13182/NSE69-A19723
Calculation of Temperature Distributions in Fuel Rods with Varying Conductivity and Asymmetric Flux Distribution
D. G. Andrews, M. Dixmier
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 259-267
Technical Paper | doi.org/10.13182/NSE69-A18722
The Computation of the Equilibrium Vapor Composition Over UO2 + x
M. H. Fontana, R. E. Bailey
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 268-274
Technical Paper | doi.org/10.13182/NSE69-A18723
Elastic and Inelastic Scattering of Fast Neutrons from 10B, 11B, Natural Ge, and 93NB
John C. Hopkins, D. M. Drake
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 275-279
Technical Paper | doi.org/10.13182/NSE69-A18724
The 14N(n, xγ) Reaction for 5.8 ≤ En ≤ 8.6 MeV
J. K. Dickens, F. G. Perey
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 280-290
Technical Paper | doi.org/10.13182/NSE69-A18725
Calculation of the Neutron and Proton Spectra from Thick Targets Bombarded by 450-MeV Protons and Comparison with Experiment
R. G. Alsmiller, Jr., J. W. Wachter, H. S. Moran
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 291-294
Technical Paper | doi.org/10.13182/NSE69-A18726
A Numerical Treatment of the Attenuation of Neutrons by Air Ducts in Shields
Ricardo Artigas, H. E. Hungerford
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 295-303
Technical Paper | doi.org/10.13182/NSE69-A18727
Advantages of Using a Combination Electromagnetic and Material Shield
R. D. Shelton, H. E. Stern, J. W. Watts
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 304-308
Technical Paper | doi.org/10.13182/NSE69-A18728
Neutron Flux and Importance Distribution by Collision Method, Starting from a Generalized Source
G. Bitelli, M. Salvatores
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 309-314
Technical Paper | doi.org/10.13182/NSE69-A18729
Discrete Energy Representation of Thermal-Neutron Spectra in Uranium-Plutonium Lattices
B. Fredin, T. Boševski, M. Mataušek
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 315-325
Technical Paper | doi.org/10.13182/NSE69-A18730
Neutron Diffusion in Aluminum-Water Lattices: Measurements of Anisotropy in the Continuous Eigenvalue Region
Philip F. Palmedo, John F. Conant
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 326-335
Technical Paper | doi.org/10.13182/NSE69-A18731
A Detailed Method for Calculating the Low Energy Multigroup Cross Sections and the Doppler Coefficient in a Fast Reactor
C. R. Adkins, T. E. Murley, M. W. Dyos
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 336-350
Technical Paper | doi.org/10.13182/NSE69-A18732
Neutron Rethermalization Near a Temperature Discontinuity Between Terphenyl and Light Water
A. Rastas, J. Saastamoinen
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 351-360
Technical Paper | doi.org/10.13182/NSE69-A18733
On Transient Digital Control of a Linear Model of the Halden Boiling Water Reactor
W. Ciechanowicz, K. O. Solberg
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 361-371
Technical Paper | doi.org/10.13182/NSE69-A18734
A Three-Dimensional Analysis of Xenon-Induced Oscillations in Boiling Water Cooled Reactors
Wataru Shinoda, Susumu Mitake
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 372-388
Technical Paper | doi.org/10.13182/NSE69-A18735
Stochastic Kinetic Theory for a Space- and Energy-Dependent Zero Power Nuclear Reactor Model
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 389-401
Technical Paper | doi.org/10.13182/NSE69-A18736
Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics
K. O. Ott, D. A. Meneley
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 402-411
Technical Paper | doi.org/10.13182/NSE36-402
Analytical and Experimental Investigations of the Kinetic Behavior of a Uranium-Dioxide-Fueled Pressurized-Water Reactor
J. E. Houghtaling, J. E. Grund
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 412-426
Technical Paper | doi.org/10.13182/NSE69-A18738
Pressure Pulse Propagation in an Annular Flowing Two-Phase System
C. W. Garrard, Jr., R. S. Wick
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 427-429
Technical Note | doi.org/10.13182/NSE69-A18739
A Systematic Comparison of Different Hydrodynamics Models
Rainer Grumbach
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 429-433
Technical Note | doi.org/10.13182/NSE69-A18740
Monatomic Gas Cross Section Expansion Coefficients
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 433-434
Technical Note | doi.org/10.13182/NSE69-A18741
Selected Fission Cross Sections for 236U
William G. Davey
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 434-435
Technical Note | doi.org/10.13182/NSE69-A18742
Space-Angle Synthesis
Harry S. Zwibel, Bradley Bowes
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 435-438
Technical Note | doi.org/10.13182/NSE69-A18743
Source Convergence in Monte Carlo Calculations
L. L. Carter, N. J. McCormick
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 438-441
Technical Note | doi.org/10.13182/NSE69-1
Single Rod Fine Distribution of the Fast Fission Ratio
V. Aiello, G. Maracci, F. Rustichelli
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 441-444
Technical Note | doi.org/10.13182/NSE69-A18745
An Anomaly Arising in the Collapsed-Group Flux Synthesis Approximation
C. H. Adams, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 444-447
Technical Note | doi.org/10.13182/NSE69-A18746
Application of the jN Method to Neutron Transport in Slabs and Spheres
H. Kschwendt
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 447-450
Technical Note | doi.org/10.13182/NSE69-A18748
On the Milne-Problem Extrapolation Distance
G. R. Bond, C. E. Siewert
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Page 447
Technical Note | doi.org/10.13182/NSE69-A18747
Equivalence of Integral Transform and Spatial Spherical Harmonics Methods
J. Mika, R. Stankiewicz
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 450-453
Technical Note | doi.org/10.13182/NSE69-A18749
Collisional Importance and Adjoint Problems in Neutron Transport
Paul Nelson, Jr.
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 453-455
Technical Note | doi.org/10.13182/NSE69-A18750