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Number 1
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Number 3

Number 1

Table of Contents
ATHENA (D. Spielberg)
Nuclear Matter and Nuclear Reactions (William E. Kiker)
Determination of Reactor Kinetic Parameters by Photon Observation (Wayne K. Lehto, John M. Carpenter)
The Constructive Uses of Nuclear Explosives (Paul Kruger)

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
R. N. Hwang
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

Number 2

Table of Contents
Moderator Studies for a Repetitively Pulsed Test Facility (RPTF) (R. G. Fluharty, F. B. Simpson, G. J. Russell, J. H. Menzel)
TWOTRAN (x, y) (K. D. Lathrop)
GAKIT (R. Froehlich, S. R. Johnson, M. H. Merrill)

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

Number 3

Table of Contents
Noah (G. S. Lellouche)
On Rafalski's Solution to the Albedo Problem (G. C. Pomraning)
Peter Kapitsa, on Life and Science (Don M. Yost)
Theory of Turbulent Plasma (Albert Simon)
Nuclear Chemistry (Richard L. Hahn, Curtis E. Bemis, Jr.)
Radiation Chemistry (C. J. Hochanadel)
Fabrication of Thorium Fuel Elements (David H. Gurinsky)

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 UO_{2 + 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 ≤ E_n ≤ 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
W. W. Clendenin
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 j_N 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