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Volume 15

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Number 1

Table of Contents
A Note on a Simple Method for Acceleration of Finite-Difference Group-Diffusion Calculations(Melvin Tobias, David R. Vondy, Tom B. Fowler)
DancofF Correction for Several Infinitely Long Cylindrical Rings(G. Velarde)
Neutron Absorber Materials for Reactor Control.(John R. Weeks)
Selected Papers on New Techniques for Energy Conversion.(R. L. Mela)
The Metal Plutonium.(James F. Schumar)
ZORCH(C. W. Nestor, Jr.)
GMCM-9(M. J. Kniedler)

On the Theory of Space Dependent Neutron Spectra in Heterogeneous Reactors

Helmut Kunze

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE63-A26258

The Time Decay Constants in Neutron Thermalization

Noel Corngold, Paul Michael, Warren Wollman

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 13-19

Technical Paper / dx.doi.org/10.13182/NSE63-A26259

Interaction of Fissionable Units

Hugh K. Clark

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 20-28

Technical Paper / dx.doi.org/10.13182/NSE63-A26260

The Thermal Utilization and Flux Ratios in Complex Lattices

A. PAZY

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 29-36

Technical Paper / dx.doi.org/10.13182/NSE63-A26261

Self-Limiting Power Excursion Tests of a Water-Moderated Low-Enrichment UO₂ Core

A. H. Spano

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 37-51

Technical Paper / dx.doi.org/10.13182/NSE63-A26262

Equations for Bilateral Heat Transfer to a Fluid Flowing in a Concentric Annulus

O. E. Dwyer

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 52-57

Technical Paper / dx.doi.org/10.13182/NSE63-A26263

Unilateral Heat Transfer to Liquid Metals Flowing in Annuli

O.E. Dwyer, P. S. Tu

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 58-68

Technical Paper / dx.doi.org/10.13182/NSE63-A26264

Low Temperature Galvanomagnetic Properties of Graphites

G. L. Montet

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 69-80

Technical Paper / dx.doi.org/10.13182/NSE63-A26265

Energy Deposition by Fast Neutrons: NO₂ Production in Liquid Air

Robert C. Axtmann, John, Bridgwater

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 81-89

Technical Paper / dx.doi.org/10.13182/NSE63-A26266

Deuterium Enrichment in the Distillation of Ammonia

Gerald, T. Petersen, Manson, Benedict

Nuclear Science and Engineering / Volume 15 / Number 1 / January 1963 / Pages 90-97

Technical Paper / dx.doi.org/10.13182/NSE63-A26267

Number 2

Table of Contents
An Upper Limit for the Effective Capture Cross Section of Po²¹⁰ for Thermal Neutrons(J. Halperin, J. H. Oliver)
Radiation Damage to Freon-11, CCI₃F(M. D. Silverman, B. O. Heston, P. S. Rudolph)
Determinations of the Total Emissivity of Polished and Oxidized Uranium Surfaces(L. Baker, Jr., E. M. Mouradian, J. D. Bingle)
Note on Spectrum Hardening for Non 1/v Cross Sections(W. Clendenin)
The Time Scale of Neutron Slowing Down in Water(E. Möller,, N. G. SjöStrand)
Nuclear Propulsion for Merchant Ships(Wm. B. Cottrell)
Space Research II: Proceedings of the Second International Space Science Symposium, Florence, April 10–14, 1961(Herbert Goldstein)
Tritium in the Physical and Biological Sciences(D. E. Hull, B. A. Fries)
Physics of Fast and Intermediate Reactors, Volume II(M. M. Levine)
EQUIPOISE BURNOUT(D. R. Vondy, T. B. Fowler)
Erratum: A New Method for Measuring Thermalization Parameters

Elementary Methods of Reactor Noise Analysis

Joseph A. Thie

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 109-114

Technical Paper / dx.doi.org/10.13182/NSE63-A26408

The Angular Dependence of Thermal Neutron Spectra in Lattices

Henry C. Honeck, Hiroshi Takahashi

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 115-123

Technical Paper / dx.doi.org/10.13182/NSE63-A26409

Behavior of Iodine and Xenon in the Homogeneous Reactor Test

William D. Burch, Lawrence B. Shappert

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 124-130

Technical Paper / dx.doi.org/10.13182/NSE63-A26410

At-Power, Low-Frequency, Reactor-Power-Spectrum Measurements and Comparison with Oscillation Measurements

C.W. Griffin, R. L. Randall

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 131-138

Technical Paper / dx.doi.org/10.13182/NSE63-A26411

Adjoint Functions and Orthogonality Relations

K. F. Hansen, M. Clark, Jr.

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 139-141

Technical Paper / dx.doi.org/10.13182/NSE63-A26412

Generalized Quota Sampling

Herbert A. Steinberg

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 142-145

Technical Paper / dx.doi.org/10.13182/NSE63-A26413

Measurements of the Temperature Coefficient of Resonance Absorption in Uranium Metal and Uranium Oxide

B.L. Palowitch, F. S. Frantz, Jr.

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 146-157

Technical Paper / dx.doi.org/10.13182/NSE63-A26414

The Transport Approximation of the Energy-Dependent Boltzmann Equation

G. Rakavy, Y. Yeivin

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 158-160

Technical Paper / dx.doi.org/10.13182/NSE63-A26415

Convergence Improvement of Disadvantage Factors by the Use of Even Order Spherical Harmonics Approximations

John O. Mingle

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 161-165

Technical Paper / dx.doi.org/10.13182/NSE63-A26416

Kinetics of Low Source Reactor Startups. Part I

H. Hurwitz, Jr., D. B. MacMillan, J. H. Smith, M. L. Storm

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 166-186

Technical Paper / dx.doi.org/10.13182/NSE63-3

Kinetics of Low Source Reactor Startups. Part II

H. Hurwitz, Jr.

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 187-196

Technical Paper / dx.doi.org/10.13182/NSE63-4

Linear Stability of the Thermal Flux in a Reflected Core Containing Xenon and Temperature Reactivity Feedback

Louis M. Shotkin, Frederick H. Abernathy

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 197-212

Technical Paper / dx.doi.org/10.13182/NSE63-A26419

Average Number of Prompt Neutrons Emitted in the Spontaneous Fission of U²³⁸ and Pu²⁴⁰

I. Asplund-Nilsson, H. Condé, N. Starfelt

Nuclear Science and Engineering / Volume 15 / Number 2 / February 1963 / Pages 213-216

Technical Paper / dx.doi.org/10.13182/NSE63-A26420

Number 3

Table of Contents
Xenon Poisoning in a Shut-Down Reactor(H. Albers, Z. J. Doron, W. Hälg S. Ravani)
Nonperturbing Foils-An Experimental Verification(J. D. Randall, J. V. Walker)
Beta Decay for Pedestrians(Rudolph Sher)

A Comment on the Collision Density at Epithermal Energies

Coleridge A. Wilkins, A. Keane

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 229-232

Technical Paper / dx.doi.org/10.13182/NSE63-A26433

The Measurement of the Lattice Parameters of a Gas Cooled Reactor Lattice

P. F. Nichols, J. R. Worden, F. C. Engesser, R. E. Heineman

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 233-244

Technical Paper / dx.doi.org/10.13182/NSE63-A26434

A Discussion of Theoretical Analyses of Probe-Induced Thermal Flux Perturbations

R. K. Osborn

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 245-258

Technical Paper / dx.doi.org/10.13182/NSE63-A26435

Application of the Spherical Harmonics Technique to Problems in Gamma Transport

W. D. Lanning

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 259-267

Technical Paper / dx.doi.org/10.13182/NSE63-A26436

A Method for the Accurate Determination of Relative Initial Conversion Ratios

P. R. Tunnicliffe, D. J. Skillings, B. G. Chidley

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 268-283

Technical Paper / dx.doi.org/10.13182/NSE63-A26437

The Mass Spectrometric Determination of the Cs¹³⁷ Half-Life

B.F. Rider, J. P. Peterson, Jr., C. P. Ruiz

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 284-287

Technical Paper / dx.doi.org/10.13182/NSE63-A26438

Rates and Mechanisms of the Loss of Fission Products from Uranium-Graphite Fuel Materials

E. A. Bryant, G. A. Cowan, J. E. Sattizahn, Kurt Wolfsberg

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 288-295

Technical Paper / dx.doi.org/10.13182/NSE63-A26439

Time-Dependent Neutron Thermalization for a Bare Multiplying Medium

Edward Garelis

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 296-304

Technical Paper / dx.doi.org/10.13182/NSE63-A26440

The Effect of Inlet Spacing Deviations on the Flow-Induced Deflections of Flat Plates

J. J. Kane

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 305-308

Technical Paper / dx.doi.org/10.13182/NSE63-A26441

Thermal Neutron Flux Perturbation Due to Indium Foils in Water

Jack V. Walker, John D. Randall, Ronald C. Stinson, Jr.

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 309-313

Technical Paper / dx.doi.org/10.13182/NSE63-A26442

Effective Cutoff Energies for Boron, Cadmium, Gadolinium, and Samarium Filters

R. W. Stoughton, J. Halperin

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 314-324

Technical Paper / dx.doi.org/10.13182/NSE63-A26443

The Neutron Flux Perturbation Due to an Absorbing Foil; A Comparison of Theories and Experiments

G. C. Hanna

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 325-337

Technical Paper / dx.doi.org/10.13182/NSE63-A26444

Stream Flow Measurement by an Inert Tracer Pulse Technique

R. P. Gardner, J. W. Dunn, III

Nuclear Science and Engineering / Volume 15 / Number 3 / March 1963 / Pages 338-341

Technical Paper / dx.doi.org/10.13182/NSE63-A26445

Number 4

Table of Contents
On the Energy-Dependent Transport Equation(G. C. Summerfield, P. F. Zweifel)
Nuclear Reactor Fuel Elements, Metallurgy and Fabrication(Charles R. Johnson)
Small and Medium Power Reactors, Proceedings of the Vienna Conference, September 1960(W. Kenneth Davis, Tarsem S. Purewal)
Materials Science and Technology for Advanced Applications(E. Creutz)
Self-Limiting Power Excursion Tests of a Water Moderated Low-Enrichment UO₂ Core(A. H. Spano)
Erratum: Measurements of the Temperature Coefficient of Resonance Absorption in Uranium Metal and Uranium Oxide(B. L. Palowitch, F. S. Feantz, Jr)

Design of a Small Aqueous Homogeneous Breeder Reactor

R. H. Chapman, I. Spiewak, M. L. Tobias, D. R. Vondy

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 347-353

Technical Paper / dx.doi.org/10.13182/NSE63-A26450

The Mechanism of Extraction by Tributyl Phosphate-n-Hexane Solvents: Part II. Nitric Acid Extraction

Donald R. Olander, Manson Benedict

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 354-365

Technical Paper / dx.doi.org/10.13182/NSE63-A26451

Some Nuclear-Chemical and Physicochemical Problems in Fission-Product Recoil Separation

Ury Passy, Naftali H. Steiger

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 366-374

Technical Paper / dx.doi.org/10.13182/NSE63-A26452

The Investigation of Neutron Kinetics and Cross Sections in Fast Nonmoderating Assemblies by the Nanosecond Pulsed Neutron Source Technique

L. E. Beghian, N. C. Rasmussen, R. Thews, J. Weber

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 375-381

Technical Paper / dx.doi.org/10.13182/NSE63-A26453

Epithermal Neutron Absorption in Slab Lattices

M. Goldsmith

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 382-387

Technical Paper / dx.doi.org/10.13182/NSE63-A26454

Burning Temperatures of Uranium and Zirconium in Air

Edward M. Mouradian, Louis Baker, Jr.

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 388-394

Technical Paper / dx.doi.org/10.13182/NSE63-A26455

Burning Velocities of Uranium and Zirconium in Air

L. Leibowitz, L. Baker, Jr., J. G. Schnizlein, L. W. Mishler, J. D. Bingle

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 395-403

Technical Paper / dx.doi.org/10.13182/NSE63-A26456

The Effect of Halogenated Hydrocarbons on the Burning of Uranium and Zirconium

L. Leibowitz, J. G. Schnizlein, L. W. Mishler

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 404-410

Technical Paper / dx.doi.org/10.13182/NSE63-A26457

Neutron Radiographic Inspection of Radioactive Irradiated Reactor Fuel Specimens

Harold Berger, W. N. Beck

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 411-414

Technical Paper / dx.doi.org/10.13182/NSE63-A26458

Equipment Used in the Performance of Experiments in Nuclear Reactors at the Argonne National Laboratory

E. S. Sowa, C. R. Breden, L. W. Fromm, Jr.

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 415-428

Technical Paper / dx.doi.org/10.13182/NSE63-A26459

Calculation of Partial Differential Scattering Cross Sections for Slow Neutrons

H. L. McMurry

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 429-437

Technical Paper / dx.doi.org/10.13182/NSE63-A26460

Evaluation of Techniques for Computing Partial Differential Scattering Cross Sections

H. L. McMurry, L. J. Gannon, W. A. Hestir

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 438-450

Technical Paper / dx.doi.org/10.13182/NSE63-A26461

Solution to the Fission Recoil Energy Deposition In a Slurry by a Monte Carlo Technique

Lawrence R. Steele, Daniel Carson, Charles E. Dryden

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 451-457

Technical Paper / dx.doi.org/10.13182/NSE63-A26462

Water Decomposition by Fission Fragment Recoil Energy in an Aqueous Slurry of Uranium—Thorium Oxides

Lawrence R. Steele, Sheffield Gordon, Charles E. Dryden

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 458-467

Technical Paper / dx.doi.org/10.13182/NSE63-A26463

Analysis for Diffusion Theory Flux Peaking at a Sharp Corner

J. H. Smith

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 468-473

Technical Paper / dx.doi.org/10.13182/NSE63-A26464

A Method for Determination of Spatial Stability

Stig Lundquist, Peter Weissglas

Nuclear Science and Engineering / Volume 15 / Number 4 / April 1963 / Pages 474-475

Technical Paper / dx.doi.org/10.13182/NSE63-A26465