Home / Publications / Journals / Nuclear Science and Engineering / Volume 57

Volume 57

Number 1 | Number 2 | Number 3 | 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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE75-A15427