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Volume 16

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Number 1

Table of Contents
The Kinetic Behavior of the Coupled Regions of the UTR-10 Reactor(Richard A. Danofsky, Robert E. Uhrig)
The Convergence of the Equipoise Method(G. K. Kristiansen)
Reactor Dynamics with Reactivity Loss Rate Proportional to Energy(J. Ernest Wilkins, JR.)
Sintering of UO₂ in Carbon Dioxide Atmosphere(I. Amato, R. L. Colombo, A. M. Protti)
A Remark on the Measurement of the Diffusion Coefficient for Thermal Neutrons(Henry C. Honeck, Paul Michael)
Re: A Remark on the Measurement of the Diffusion Coefficient for Thermal Neutrons(N. P. Baumann)
1960 Nuclear Data Tables; Part 4, Short Tables(A. B. Smith)
The Collected Papers of Enrico Fermi, Volume 1, Italy 1921–1938(Robert R. Wilson)
Radiation Chemistry of Polymeric Systems(Vincent P. Calkins)

Surface Electrical Studies of Plutonia and Thoria Suspensions, Part I

R. G. Sowden, K. E. Francis

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 1-11

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Surface Electrical Studies of Thoria and Plutonia Suspensions, Part II

R. G. Sowden, B. R. Harder, K. E. Francis

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 12-24

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A Mathematical Model for the Solvent Extraction of Uranyl Nitrate and Nitric Acid

M. H. Lletzke, R. W. Stoughton, Marjorie P. Lietzke

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 25-30

Technical Paper / dx.doi.org/10.13182/NSE63-A26475

Effects of Boundary Layer Turbulence Promoters on the Local Film Coefficients of ML-1 Fuel Elements

N. Kattchee, W. V. Mackewicz

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 31-38

Technical Paper / dx.doi.org/10.13182/NSE63-A26476

Neutron Temperatures in a CANDU-Type Power Reactor

B. G. Chidley, R. B. Turner, C. B. Bigham

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 39-67

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The Slowing-Down Spectrum in a CANDU-Type Reactor

C. B. Bigham, B. G. Chidley, R. B. Turner

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 68-84

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Neutron Temperature Distributions in a Cylinder of Hot Moderator

C. B. Bigham, R. B. Turner, B. G. Chidley

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 85-100

Technical Paper / dx.doi.org/10.13182/NSE63-A26479

A Method of Solving the Time Dependent Neutron Thermalization Problem

J. U. Koppel

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE63-A26480

On the Estimation of Flux at a Point by Monte Carlo

M. H. Kalos

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 111-117

Technical Paper / dx.doi.org/10.13182/NSE63-A26481

Probability Distribution of Neutrons and Precursors in Multiplying Medium

George I. Bell, W. A. Anderson, D. Galbraith

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 118-123

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An Absolute Measurement of of Cf²⁵²

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

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 124-130

Technical Paper / dx.doi.org/10.13182/NSE63-A26483

Number 2

Table of Contents
On the Linear Extrapolation Distance(G. C. Pomraning)
On the Existence of Tributyl Phosphate Monohydrate(Robert C. Axtmann)
Reply to Preceding Letter “On the Existence of Tributyl Phosphate Monohydrate”(D. R. Olander)
Effect of Temperature Variation on “Intermediate-Resonance” Formulas(M. H. McKay, J. P. Pollard)
The Average Capture/Fission Ratio of U²³³ for Epithermal Neutrons(J. Halperin, F. J. Johnston, R. W. Stoughton, J. H. Oliver, E. L. Blevins, R. E. Druschel, A. L. Harkness, B. A. Swarz)
The O¹⁶(n,p) N¹⁶ Reaction Cross Section(K. Shure)
Cadmium Ratios of U²³⁵ Fission in Slightly Enriched Uranium, Light Water Moderated Lattices(S. Tassan)
Physics of Fast and Intermediate Reactors, Volume III(Joseph R. Dietrich)
Fast Reactors(Walter J. McCarthy, Jr.)
Principles of Cyclic Particle Accelerators(H. G. Blosser)
(Newnes) Concise Encyclopaedia of Nuclear Energy(Everitt P. Blizard)
International Directory of Radioisotopes(Marshall Brucer)
Adventures in Radioisotope Research(Marshall Brucer)
Directory of Nuclear Reactors, Vol. IV(J. A. Lane)
PLATYPUS(J. M. Illingworth)
M0332(R. M. Cantwell)
GAZE-II(S. R. Lenihan)
SPMCN-1(M. J. Kniedler)
M0322(R. M. Cantwell)
PLMCN-1(M. J. Kniedler)
Erratum: Kinetics of Low Source Reactor Startups, Part I

The Variational Method Applied to the Monoenergetic Boltzmann Equation. Part I

G. C. Pomraning, M. Clark, Jr.

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 147-154

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The Variational Method Applied to the Monoenergetic Boltzmann Equation. Part II

G. C. Pomraning, M. Clark, Jr.

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 155-164

Technical Paper / dx.doi.org/10.13182/NSE63-A26495

Calculation of Thermal Neutron Flux Spectra in a Polyethylene Moderated Medium

D. T. Goldman, F. D. Federighi

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 165-175

Technical Paper / dx.doi.org/10.13182/NSE63-A26496

An Application of a New Method for the Solution of Group Diffusion Equations to a Cylindrical Flux Trap Assembly with Spontaneous Fission Source

Timo Toivanen

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 176-185

Technical Paper / dx.doi.org/10.13182/NSE63-A26497

Experimental Bucklings and Void Effects in Heavy Water Lattices of Natural Uranium Oxide Rod Clusters

W. E. Graves, H. R. Fike, G. F. O'Neill

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 186-195

Technical Paper / dx.doi.org/10.13182/NSE63-A26498

Temperature Dependence of the Neutron Transport Cross Section in Polyethylene and Paraffin

L. J. Esch

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 196-201

Technical Paper / dx.doi.org/10.13182/NSE63-A26499

Accurate Doppler Broadened Absorption

G. W. Hinman, G. F. Kuncir, J. B. Sampson, G. B. West

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 202-207

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Bang-Bang Control of Boiling Moderator Nuclear Reactors

Milton Ash

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 208-212

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Radiation Nucleation of Bubbles in Water

Amos Norman, P. Spiegler

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 213-217

Technical Paper / dx.doi.org/10.13182/NSE63-A26502

Flow Induced Deflections of Parallel Flat Plates

R. D. Groninger, J. J. Kane

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 218-226

Technical Paper / dx.doi.org/10.13182/NSE63-A26503

Importance Sampling in Monte Carlo Shielding Calculations: I. Neutron Penetration through Thick Hydrogen Slabs

M. H. Kalos

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 227-234

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Numerical Determination of Flux Perturbation by Foils

Friedrich H. Helm

Nuclear Science and Engineering / Volume 16 / Number 2 / June 1963 / Pages 235-238

Technical Paper / dx.doi.org/10.13182/NSE63-A26505

Number 3

Table of Contents
Xenon Oscillations in Finite Reactors(R. M. Pearce)
A Sulfur-Phosphorus Absolute Fast Neutron Flux Detector(G. A. Gilmour)
Resonance Absorption in Materials with Grain Structure (Addendum)(L. W. Nordheim)
Mathematics for the Physical Sciences(Noel Corngold)
The Theory of Plasma Waves(Albert Simon)
Proceedings of the International School of Physics “Enrico Fermi,” Varenna, Italy. Course 15: Nuclear Spectroscopy(David T. Goldman)
Mechanical Properties of Metals(S. W. Porembka)

Thermal Self-Shielding and Edge Effects in Absorbing Foils

J. L. Crane, R. C. Doerner

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 259-262

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Theory of Pulsed Neutron Source Measurements

Edward Garelis, John L. Russell, Jr.

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 263-270

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Resonance Integral Calculations for U²³⁸ Lattices

Melvin M. Levine

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 271-279

Technical Paper / dx.doi.org/10.13182/NSE63-A26530

Coating Costs for Ceramic-Coated Nuclear-Fuel Particles

J. H. Oxley, M. F. Browning, J. M. Blocker, Jr., C. E. Dryden

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 280-290

Technical Paper / dx.doi.org/10.13182/NSE63-A26531

Superprompt-Critical Behavior of an Unmoderated, Unreflected Uranium—Molybdenum Alloy Reactor

John T. Mihalczo

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 291-298

Technical Paper / dx.doi.org/10.13182/NSE63-A26532

Effective Fission Cross Sections and Neutron Spectra in an NRX Type Uranium Metal Rod

C. B. Bigham, S. A. Kushneriuk, P. R. Tunnicliffe

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 299-314

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Fission Fragment Distribution in Irradiated UO₂

R. M. Berman

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 315-328

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Approximate Escape Probabilities

A. Sauer

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 329-335

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Number 4

Table of Contents
A Comparison of the Transfer Function of the Internal Reactor Loop for the Cases of both Distributed and Lumped Parameters(W. Clechanowicz)
The Fuchs—Nordheim Model with Variable Heat Capacity(R. Scalettar)
Green's Function for a Bare Slab with Anisotropic Scattering(J. J. McInerney)
Uranium and Graphite(S. H. Bush)
Reactor Handbook, Vol. III, Part B. Shielding(C. C. Horton)
Metallurgy and Metallography of Pure Metals(John R. Weeks)
Advances in Computers, Volume 3(Ward Sangren)
Rare Earth Research(Don M. Yost)

A Variational Procedure for Calculating Fast Group Constants

P. A. Ombrellaro, F. D. Federighi

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 343-356

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Fission Plate Power Measurement by a Transient-Temperature Method

James N. Anno

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 357-362

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Some Problems Concerning the Theory of Pulsed Neutron Experiments

P. Vértes

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 363-368

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Kinetics of Low Source Reactor Startups—Part III

D. B. MacMillan, M. L. Storm

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 369-380

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Solvent Extraction Chemistry Symposium

K. B. Brown

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Page 381

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Some Mechanisms of Extraction of M(II), (III), (IV), and (VI) Metals by Acidic Organophosphorus Extractants

D. F. Peppard, G. W. Mason

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 382-388

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Structural Aspects of Organophosphorus Extractants and Their Metallic Complexes as Deduced from Spectral and Molecular Weight Studies

J. R. Ferraro, D. F. Peppard

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 389-400

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Alkylphosphoric Acids and Their Complexes with Metals

C. J. Hardy

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 401-404

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The Synergistic Effects in Organophosphate Extraction Systems

C. F. Baes, Jr.

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 405-412

Technical Paper / dx.doi.org/10.13182/NSE63-A26552

Synergism with Thenoyl Trifluoracetone in the Solvent Extraction of Metallic Species

T. V. Healy

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 413-420

Technical Paper / dx.doi.org/10.13182/NSE63-A26553

Extraction of Metal Nitrates by TBP·HNO₃

J. M. Fletcher, C. J. Hardy

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 421-427

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The Neutral Organophosphorus Compounds as Extractants

L. L. Burger

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 428-439

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Extraction with Sulfur-Containing Organophosphorus Compounds

Thomas H. Handley

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 440-447

Technical Paper / dx.doi.org/10.13182/NSE63-A26556

The Use of Solvent Extraction Techniques in the Study of Chemical Equilibria

David Dyrssen

Nuclear Science and Engineering / Volume 16 / Number 4 / August 1963 / Pages 448-455

Technical Paper / dx.doi.org/10.13182/NSE63-A26557