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Volume 55

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Number 1

Table of Contents
Variational Methods in Nuclear Reactor Physics.(Jeffery Lewins)
Topics in Radiation Dosimetry (Radiation Dosimetry, Supplement 1).(J. E. Turner)

Initial Voiding Experiments with Sodium Under Liquid-Metal Fast Breeder Reactor Conditions

D. M. France, R. D. Carlson, R. R. Rohde, G. T. Charmoli

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE74-A23959

A Kinetic Theory for the Annealing of Radiation Damage in Germanium

W. Maurice Pritchard, James L. Reid

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 11-16

Technical Paper / dx.doi.org/10.13182/NSE74-A23960

Improved Activation Measurements of (n, γ) Cross Section for 14.6-MeV Neutrons

F. Rigaud, M. G. Desthuilliers, G. Y. Petit, J. L. Irigaray, G. Longo, F. Saporetti

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 17-23

Technical Paper / dx.doi.org/10.13182/NSE55-17

Cross-Section Measurement of Plutonium-236 Formation in Plutonium-238 by ²³⁷Np(n, 2n)Reactions

C. K. Paulson, E. J. Hennelly

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 24-27

Technical Paper / dx.doi.org/10.13182/NSE74-A23962

Spectrum of Delayed Neutrons from the Thermal-Neutron Fission of Uranium-235

W. Robert Sloan, Gene L. Woodruff

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 28-40

Technical Paper / dx.doi.org/10.13182/NSE74-A23963

Angular Distribution Measurements of Secondary-Particle Fluxes with Spallation Detectors and Comparisons to Hadron Cascade Calculations

J. T. Routti

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 41-50

Technical Paper / dx.doi.org/10.13182/NSE74-A23964

Criticality of Plutonium-Uranium Mixtures Containing 5 to 8 wt% Plutonium

R. C. Lloyd, S. R. Bierman, E. D. Clayton

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 51-57

Technical Paper / dx.doi.org/10.13182/NSE74-A23965

Critical Experiments to Measure the Neutron Poisoning Effects of Copper and Copper-Cadmium Plates

S. R. Bierman, E. D. Clayton

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 58-66

Technical Paper / dx.doi.org/10.13182/NSE74-A23966

Calculation of Electron Transport in a Slab

O. B. Evdokimov, A. P. Yalovets

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 67-75

Technical Paper / dx.doi.org/10.13182/NSE74-A23967

Analytic X-Ray Transport Theory for Numerical Computation

Randall K. Cole, Jr.

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 76-84

Technical Paper / dx.doi.org/10.13182/NSE74-A23968

Lifetime-Averaged Cross Sections for X-Ray Transport Calculations

Randall K. Cole, Jr.

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 85-88

Technical Paper / dx.doi.org/10.13182/NSE74-A23969

Calculations of a Fast-Neutron Shielding Experiment for Evaluating Approximate Shielding Design Methods

C. R. Adkins

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 89-96

Technical Note / dx.doi.org/10.13182/NSE74-A23970

Evaluation of Integrals by Differentiation with Application to Collision Methods

G. Bitelli, A. Turrin

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 96-97

Technical Note / dx.doi.org/10.13182/NSE74-A23971

An Accelerated Spectral Synthesis Technique

William G. Price, Jr., James J. Duderstadt

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 98-102

Technical Note / dx.doi.org/10.13182/NSE74-A23972

Comparative Analysis of Neutron Data Files as a Sensitivity Study

M. Segev, S. Yiftah, Y. Gur, L. Gitter

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 103-104

Technical Note / dx.doi.org/10.13182/NSE74-A23973

Measurement of Anisotropic Neutron Diffusion Coefficients in Square Lattices of Aluminum in Light Water by the Pulsed Neutron Method

Yoshihiko Kaneko, Fujiyoshi Akino, Yoshiro Suzuoki, Kenji Kitadate, Ryosuke Kurokawa,Kinji Koyama

Nuclear Science and Engineering / Volume 55 / Number 1 / September 1974 / Pages 105-116

Technical Note / dx.doi.org/10.13182/NSE74-A23974

Number 2

Table of Contents
Calculation of Temperature Distributions in Fuel Rods with Varying Conductivity and Asymmetric Flux Distribution(D. G. Andrews, M. Dixmier, D. G. Andrews, M. Dixmier)
An Asymptotic Solution in the Theory of Neutron Moderation(C. E. Siewert and A. R. Burkart, C. E. Siewert, A. R. Burkart)
Comments on “A Method of Computing Fission-Product Decay Heat in a Reactor with Time-Dependent Flux”(K. Shure)

Space-Time Nuclear Reactor Analysis by Temporal Transformation

W. J. Garland, A. A. Harms, J. Vlachopoulos

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 119-128

Technical Paper / dx.doi.org/10.13182/NSE74-A28202

Measurements at the Critical Facility for the In-Core Thermionic Reactor and Comparison with Calculations

M. Bloser, N. Kirch, F. J. Krings, A. Naseband, N. Paul

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 129-146

Technical Paper / dx.doi.org/10.13182/NSE74-A28203

Radiation-Transport Cross-Section Sensitivity Analysis— A General Approach Illustrated for a Thermonuclear Source in Air

D. E. Bartine, E. M. Oblow, F. R. Mynatt

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 147-167

Technical Paper / dx.doi.org/10.13182/NSE74-A28204

Gamma-Ray-Production Cross Sections for the ⁵⁶Fe(n,n’y) Reaction from 2.5- to 14.1-MeV Neutron Energies

J. Lachkar, J. Sigaud, Y. Patin, G. Haouat

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 168-187

Technical Paper / dx.doi.org/10.13182/NSE74-A28205

Prompt-Neutron Yield from the Spontaneous Fission of Californium-252

J. W. Boldeman

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 188-202

Technical Paper / dx.doi.org/10.13182/NSE74-A28206

Measurement of the Fission Cross Section of Uranium-235 for Incident Neutrons with Energies Between 2 and 100 keV

R. B. Perez, G. de Saussure, E. G. Silver, R. W. Ingle, H. Weaver

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 203-218

Technical Paper / dx.doi.org/10.13182/NSE74-A28207

Optimum Active-Inactive Times in Supervised Protective Systems for Nuclear Reactors

J. M. Kontoleon, Nadia Kontoleon, N. G. Chrysochoides

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 219-224

Technical Paper / dx.doi.org/10.13182/NSE74-A28208

Transport Calculations of the Neutron Escape Probability

A. M. Melandri, F. Premuda, G. P. Prelati

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 225-233

Technical Note / dx.doi.org/10.13182/NSE74-A28209

Half-Range Orthogonality Theorem for Thermal-Neutron Transport

Yuji Ishiguro

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 233-234

Technical Note / dx.doi.org/10.13182/NSE74-A28210

On the Randomness of a Neutron’s Kinetic Energy as It Slows Down by Elastic Collisions in an Infinite Medium

C. S. Barnett

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 234-242

Technical Note / dx.doi.org/10.13182/NSE74-A28211

Incomplete Neutron Thermalization in Light Water Ice at 77, 21, and 4 K

G. S. Gangwani, L. S. Kothari

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 242-243

Technical Note / dx.doi.org/10.13182/NSE74-A28212

Cross Sections of Aluminum and Iron Averaged Over the Californium-252 Fission Neutron Spectrum

W. G. Alberts, M. Matzke

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 243-244

Technical Note / dx.doi.org/10.13182/NSE74-A28213

Reexamination of the Value for the Minimum Critical Concentration of Plutonuim -239 in Water

C. R. Richey

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 244-247

Technical Note / dx.doi.org/10.13182/NSE74-A28214

Number 3

Table of Contents
REBUS-2(R. P. Hosteny, B. J. Toppels, A. P. Olson)
Experimental Neutron Resonance Spectroscopy(James Rainwater)
Nuclear Energy: Its Physics and Its Social Challenge(Ferdinand J. Shore)
Radioecology(C. W. Francis)

Coolant Flow and Reactivity Oscillations

Y. S. Lu

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 249-255

Technical Paper / dx.doi.org/10.13182/NSE74-A23451

A Comparative Study of Several Fusion Reactor Blanket Designs

M. A. Abdou, Robert W. Conn

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 256-266

Technical Paper / dx.doi.org/10.13182/NSE74-A23452

Cross-Section Requirements for Charged-Particle Fusion Reactors: The ⁶Li(p,³He)α Reaction

C. R. Gould, R. O. Nelson, J. R. Williams, J. R. Boyce

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 267-272

Technical Paper / dx.doi.org/10.13182/NSE74-A23453

The Neutron Total Cross Section of Americium-243

O. D. Simpson, F. B. Simpson, J. A. Harvey, G. G. Slaughter, R. W. Benjamin, C. E. Ahlfeld

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 273-279

Technical Paper / dx.doi.org/10.13182/NSE74-A23454

The Role of Integral Data in Neutron Cross-Section Evaluation

A. Pazy, G. Rakavy, I. Reiss, J. J. Wagschal, Atara Ya’ari, Y. Yeivin

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 280-295

Technical Paper / dx.doi.org/10.13182/NSE55-280

Binary Signals Constructed from Walsh Sequences for Reactor Dynamics Measurements

R. W. Albrecht, S. A. Wright

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 296-306

Technical Paper / dx.doi.org/10.13182/NSE74-A23456

The Time-Dependent Nuclear Reactor with Feedback

Dong H. Nguyen

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 307-319

Technical Paper / dx.doi.org/10.13182/NSE74-A23457

Solution of Two-Dimensional Diffusion Equation by the Finite Fourier Transformation

Keisuke Kobayashi, Nobuo Ohtani, Jungchung Jung

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 320-328

Technical Paper / dx.doi.org/10.13182/NSE74-A23458

A New Procedure for the Determination of Neutron Multigroup Transfer Matrices

C. R. Weisbin, P. D. Soran, J. S. Hendricks

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 329-341

Technical Paper / dx.doi.org/10.13182/NSE74-A23459

Radiation Converter Plate Design

M. S. Ash, G. Yanow

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 342-344

Technical Note / dx.doi.org/10.13182/NSE74-A23460

Measurements and Calculations of the Neutron Spectra Emitted from Concrete Spheres Bombarded with 14-MeV Neutrons

L. F. Hansen, J. D. Anderson, R. J. Doyas, R. J. Howerton, T. Komoto, C. M. Logan, C. Wong, J. L. Kammerdiener

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 345-348

Technical Note / dx.doi.org/10.13182/NSE74-A23461

Multiregion Equivalence Relation for Resonance Heterogeneity Effects

Yukio Ishiguro

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 349-351

Technical Note / dx.doi.org/10.13182/NSE74-A23462

A Simplified Derivation of the Poincaré-Bertrand Formula

L. C. Baird, P. F. Zweifel

Nuclear Science and Engineering / Volume 55 / Number 3 / November 1974 / Pages 351-353

Technical Note / dx.doi.org/10.13182/NSE74-A23463

Number 4

Table of Contents
Some Aspects of Fuel-Pin Failure Propagation in Sodium-Cooled Fast Reactors(Debaprasad Majumdar, Mujid S. Kazimi)
Reply to “Comments on Fuel-Pin-Failure Propagation”(H. K. Fauske)
The Influence of Neutron Poisons on High-Concentration Plutonium Solutions(Robert E. Rothe)
Response to “The Influence of Neutron Poisons on High-Concentration Plutonium Solutions”(R. C. Lloyd)
Plasma Engineering(Igor Alexeff)

Transport and Diffusion Equations in Toroidal Geometry

G. C. Pomraning, C. A. Stevens

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 359-367

Technical Paper / dx.doi.org/10.13182/NSE74-A23469

Investigation of the Space- and Energy-Dependent Coherence Function in Zero-Power Coupled-Core Reactors

D. D. Ebert, J. D. Clement, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 368-379

Technical Paper / dx.doi.org/10.13182/NSE74-A23470

Interpretation of Coherence Function Measurements in Zero-Power Coupled-Core Reactors

D. D. Ebert, J. D. Clement, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 380-386

Technical Paper / dx.doi.org/10.13182/NSE74-A23471

Application of the Probability Table Method to Multigroup Calculations of Neutron Transport

Dermott E. Cullen

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 387-400

Technical Paper / dx.doi.org/10.13182/NSE74-3

Measurement and Analysis of Parameters in Tight ²³²Th-²³⁵U and ²³²Th-²³³U Lattices Moderated with Heavy Water

J. Hardy, Jr., J. J. Volpe, D. Klein

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 401-417

Technical Paper / dx.doi.org/10.13182/NSE74-2

Semiclassical Description of Fast-Neutron Cross Sections

I. Angeli, J. Csikai, P. Nagy

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 418-426

Technical Paper / dx.doi.org/10.13182/NSE74-A23474

Cross Sections of Uranium-235 and Plutonium-239 for Neutrons Producing Gamma Rays

Darrell M. Drake

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 427-439

Technical Paper / dx.doi.org/10.13182/NSE74-A23475

Neutron Total Cross Section of Curium-248

R. W. Benjamin, C. E. Ahlfeld, J. A. Harvey, N. W. Hill

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 440-449

Technical Paper / dx.doi.org/10.13182/NSE74-A23476

Half-Lives of Some Cosmogenic Radionuclides: ⁷Be, ⁴⁶Sc, ⁵⁴Mn, ⁵⁶Co, and ⁶⁵Zn

Philip J. Cressy, Jr.

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 450-451

Technical Paper / dx.doi.org/10.13182/NSE74-A23477

High-Temperature Properties of Sodium for Safety Studies of Liquid-Metal Fast Breeder Reactors

A. Padilla, Jr.

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 452-461

Technical Paper / dx.doi.org/10.13182/NSE74-A23478

Thermal Fragmentation—A Gas Release Phenomenon

Michael Epstein

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 462-467

Technical Paper / dx.doi.org/10.13182/NSE74-4

Higher Order Variational Principles and Padé Approximants for Linear Functionals

Robert W. Conn

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 468-470

Technical Note / dx.doi.org/10.13182/NSE74-A23480

An Inherent Noise Analysis Investigation on the Experimental Breeder Reactor II

David D. Ebert

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 470-476

Technical Note / dx.doi.org/10.13182/NSE74-A23481

Neutron Moderation in Fast Reactors in the Presence of Wide Scattering Resonances: Analysis of Methods

G. Palmiotti, M. Salvatores

Nuclear Science and Engineering / Volume 55 / Number 4 / December 1974 / Pages 476-480

Technical Note / dx.doi.org/10.13182/NSE74-A23482