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Number 4

Number 1

Table of Contents
Computer Code: TIGER (J. A. Halbleib, Sr., W.H. Vandevender)
Book Review (F. A. Gifford)

A Technique for Calculation of Continuum Photon and Conversion-Electron Production Cross Sections and Spectra from Neutron-Induced Reactions
S. T. Perkins, R. C. Haight, R. J. Howerton
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE75-A40337
Total Neutron Cross Section of Hydrogenated Terphenyls for Neutron Energies Between 0.002 and 1.6 eV
H. A. Robitaille, J. S. Hewitt
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 12-17
Technical Paper | doi.org/10.13182/NSE75-A40338
Fission Cross Section of Uranium-235 from 3 to 20 MeV
J. B. Czirr, G. S. Sidhu
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 18-27
Technical Paper | doi.org/10.13182/NSE75-A40339
Combined Space-Time Effects of Xenon Transients and Reactor Control During Load Following in a Pebble-Bed High-Temperature Reactor
A. Lauer, W. Fröhling
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 28-38
Technical Paper | doi.org/10.13182/NSE75-A40340
A Multilevel Approach to Nuclear Fuel Burnup Optimization
W. Ciechanowicz
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 39-52
Technical Paper | doi.org/10.13182/NSE75-A40341
A New Method for the Numerical Solution of the Two-Dimensional Neutron Diffusion Equation
Katsutada Aoki, Makoto Tsuiki
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 53-62
Technical Paper | doi.org/10.13182/NSE75-A40342
Thermal-Neutron Transport Processes in Heavy Water in the Temperature Range of 253 to 4 K
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 63-74
Technical Paper | doi.org/10.13182/NSE75-A40343
Influence of Deep Minima on Multigroup Cross-Section Generation
Martin Becker
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 75-77
Technical Note | doi.org/10.13182/NSE75-A40344
Mean-Chord-Length Approximations in the Interface-Currents Formulation of the Collision-Probabilities Techniques
J. M. Sicilian, M. M. Anderson, Jr.
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 78-81
Technical Note | doi.org/10.13182/NSE75-A40345
On the Treatment of First- and Last-Collision Effects in Neutron Age Theory
Gilbert Epstein, Martin Becker
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 81-84
Technical Note | doi.org/10.13182/NSE75-A40346
Accurate Extrapolation Lengths for Pulsed Monoenergetic Neutrons in Slabs and Spheres
N. G. Sjöstrand, E. B. Dahl
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 84-86
Technical Note | doi.org/10.13182/NSE75-A40347
Some Additions to Reactor Noise Theory Which Include Delayed Neutrons
Hsiao-Kang Wang, Lawrence Ruby
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 86-90
Technical Note | doi.org/10.13182/NSE75-A40348
An Examination of the Capabilities of the Phase Space Time Evolution Method Applied to Neutron Transport
Richard B. Jones, Morton Tavel
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 90-92
Technical Note | doi.org/10.13182/NSE75-A40349
Use of the Light-Water Neutron Scattering Kernel in the Study of Neutron Transport Processes in Mixtures of Light and Heavy Water
S. P. Tewari
Nuclear Science and Engineering | Volume 57 | Number 1 | May 1975 | Pages 92-93
Technical Note | doi.org/10.13182/NSE75-A40350

Number 2

Table of Contents
The Mobility and Diffusion of Ions in Gases (Albert Simon)

Pseudorandom Multifrequency Binary Sequence Testing and State Variable, Frequency Response Analysis of a Flux-Trap Type Reactor System
W. Joe Gist, Stanley R. Bull, C. Leon Partain
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 97-116
Technical Paper | doi.org/10.13182/NSE75-A27338
Reevaluation of the Emission Probabilities of Delayed, Neutrons from Fission Products
T. Izak-Biran, S. Amiel
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 117-121
Technical Paper | doi.org/10.13182/NSE75-A27339
Comparison of the Cross-Section Sensitivity of the Tritium Breeding Ratio in Various Fusion-Reactor Blankets
R. G. Alsmiller, Jr. R. T. Santoro, J. Barish, T. A. Gabriel
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 122-128
Technical Paper | doi.org/10.13182/NSE75-A27340
Structure Shielding Against Initial Radiations from Nuclear Explosions. I. Attenuation of Air Secondary and Fission Product Gamma Rays
L. V. Spencer
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 129-154
Technical Paper | doi.org/10.13182/NSE75-A27341
Electromagnetic Self-Excitation in the Liquid-Metal Fast Breeder Reactor
E. S. Pierson
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 155-163
Technical Paper | doi.org/10.13182/NSE75-A27342
Prediction of Cross Flow Due to Coolant Channel Blockages
William D. Brown, Ehsan U. Khan, Neil E. Todreas
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 164-168
Technical Note | doi.org/10.13182/NSE75-A27343
Developing Laminar Radial Velocity Profiles and Pressure Drop in the Entrance Region of Concentric Annuli
J. E. R. Coney, M. A. I. El-Shaarawi
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 169-174
Technical Note | doi.org/10.13182/NSE75-A27344

Number 3

Table of Contents
Comments on Variational Theory and Generalized Perturbation Methods (A. Gandini)
Response to “Comments on Variational Theory and Generalized Perturbation Methods” (Weston M. Stacey, Jr.)
Variational Versus Generalized Perturbation Theories—Are They Different (E. Greenspan)
The Streaming Term of the Transport Equation in Terms of General Orthogonal Coordinates (Noel Corngold)
A Benchmark Experiment of Neutron Propagation in Iron Used to Test ENDF/B Cross-Section Data (M. Martini, G. Palmiotti, M. Salvatores)

Generalized Continuous Neutron Slowing-Down Theory
Takanobu Kamei
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 179-187
Technical Paper | doi.org/10.13182/NSE75-A26749
Elliptical Toroidal Geometry—A Geometric Transport Correction
G. C. Pomraning
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 188-195
Technical Paper | doi.org/10.13182/NSE75-A26750
Energy-Dependent Applications of the Transfer Matrix Method
Oktay I. Öztunali, Raphael Aronson
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 196-204
Technical Paper | doi.org/10.13182/NSE75-A26751
Ray-Effect Mitigation in Discrete Ordinate-Like Angular Finite Element Approximations in Neutron Transport
L. L. Briggs, W. F. Miller, Jr., E. E. Lewis
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 205-217
Technical Paper | doi.org/10.13182/NSE75-A26752
A Method of Monte Carlo Fitting
Gerald Klotzkin, Richard W. Swanson, Lawrence J. Harrison, Charles C. McPheeters
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 218-221
Technical Note | doi.org/10.13182/NSE75-A26753
An Analysis of Selected Fast Critical Assemblies Using ENDF/B-IV Neutron Cross Sections
R. W. Hardie, R. E. Schenter, R. E. Wilson
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 222-238
Technical Note | doi.org/10.13182/NSE75-A26754
Albedo-Adjusted Fast-Neutron Diffusion Coefficients in Reactor Reflectors
William B. Terney
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 239-245
Technical Note | doi.org/10.13182/NSE75-A26755
Exact Calculations of First Moment in a Simple Neutronic System
Karmeshu, N. K. Bansal
Nuclear Science and Engineering | Volume 57 | Number 3 | July 1975 | Pages 245-247
Technical Note | doi.org/10.13182/NSE75-A26756

Number 4

Table of Contents
Annual Review of Nuclear Science (W. Bennett Lewis)
Energy: Demand, Conservation, and Institutional Problems (Vance L. Sailor)
An Introduction to Fluid Mechanics and Heat Transfer (Chen Ya Liu)

Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors
Joel Weisman, Robert W. Bowring
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 255-276
Critical Review | doi.org/10.13182/NSE75-A15419
The Extended P_L Approximation of the Multidimensional Neutron Transport Equation
Beat Sigg
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 277-291
Technical Paper | doi.org/10.13182/NSE75-A15420
Perturbation Theory for Charged-Particle Transport in One Dimension
John W. Wilson, Stanley L. Lamkin
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 292-299
Technical Paper | doi.org/10.13182/NSE75-A15421
Measurements of the Neutron Capture Cross Sections of Gold-197 and Uranium-238 Between 20 and 3500 keV
W. P. Poenitz
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 300-308
Technical Paper | doi.org/10.13182/NSE75-A15422
Gamma-Ray Production Cross Sections for Iron from 0.86 to 16.7 MeV
V. J. Orphan, C. G. Hoot, V. C. Rogers
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 309-327
Technical Paper | doi.org/10.13182/NSE75-A15423
Experimental and Theoretical Studies of Criticality Safety by Ingress of Water in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel
V. Drüke, D. Filges, N. Kirch, R. D. Neef
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 328-332
Technical Paper | doi.org/10.13182/NSE75-A15424
A New Definition of the Cell Diffusion Coefficient
P. Köhler
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 333-335
Technical Notes | doi.org/10.13182/NSE75-A15425
Uranium-238 to Uranium-235 Fission-Ratio Distribution in Spherical Lithium-Metal Assemblies With and Without a Graphite Reflector
Hiroshi Maekawa, Yasushi Seki, Toru Hiraoka, Masatoshi Moriyama
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 335-340
Technical Notes | doi.org/10.13182/NSE75-A15426
Generalized Bilinear Weighting for Multigroup Cross-Section Collapsing
M. Salvatores
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 340-344
Technical Notes | doi.org/10.13182/NSE75-A15427