Home / Publications / Journals / Nuclear Science and Engineering / Volume 6

Volume 6

Number 1

Table of Contents
Thermal Neutron Inelastic Scattering Effects in a Single Crystal Neutron Spectrometer(V. P. Duggal)
Heat Transfer to Water Flowing Parallel to Tube Bundles(Joel Weisman)
The Double Spherical Harmonic Method for Cylinders and Spheres(D. W. Drawbaugh, L. C. Noderer)
The Age of U²³³ Fission Neutrons in Water(Martin Faber, P. F. Zweifel)
Note on Position-Dependent Spectra(W. B. Wright, F. Feiner)
ANS News(Octave J. DuTemple)

Nonseparable Space-Time Transients Resulting from Changes in Inlet Coolant Temperature

N. J. Curlee, Jr.

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE59-A25619

Approximate Analysis of Reactor Start-up Incidents

H. Hurwitz, Jr.

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 11-17

Technical Paper / dx.doi.org/10.13182/NSE59-A25620

Reactor Fuel Cycle Analysis by Series Methods

Raymond L. Murray, S. A. Hasnain, A. L. Mowery, Jr.

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 18-25

Technical Paper / dx.doi.org/10.13182/NSE59-A25621

A Time-Dependent Analysis of Spatial Flux Distributions

H. L. Garabedian, C. B. Leffert

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 26-32

Technical Paper / dx.doi.org/10.13182/NSE59-A25622

Gamma and Neutron Heating in and about a Homogeneous Reactor

Raymond Fox

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 33-36

Technical Paper / dx.doi.org/10.13182/NSE59-A25623

Fabrication of Zircaloy-2 Channels for Vallecitos Boiling Water Reactor Fuel Assemblies

C. N. Spalaris

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 37-43

Technical Paper / dx.doi.org/10.13182/NSE59-A25624

Calculation of MTR Fuel Loadings

H. L. McMurry, G. A. Cazier, R. W. Goin

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 44-48

Technical Paper / dx.doi.org/10.13182/NSE59-A25625

A Study of Some Mechanical, Physical, and Corrosion Properties of Iodide Hafnium

J. G. Goodwin, F. R. Lorenz

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 49-56

Technical Paper / dx.doi.org/10.13182/NSE59-A25626

Effect of (n, 2n) and (n, α) Reactions on Age Calculations for Beryllium

D. Meneghetti, H. H. Hummel

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 57-62

Technical Paper / dx.doi.org/10.13182/NSE59-A25627

Comparison Theorems for the Estimation of Average Collision Probabilities

Lawrence Dresner

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 63-65

Technical Paper / dx.doi.org/10.13182/NSE59-A25628

Solutions of the Constant Velocity Transport Problem

L. A. Beach, P. Shapiro, R. C. O'Rourke, W. R. Faust, B. Lepson

Nuclear Science and Engineering / Volume 6 / Number 1 / July 1959 / Pages 66-75

Technical Paper / dx.doi.org/10.13182/NSE59-A25629

Number 2

Table of Contents
The Transfer Function of a Water-Boiler Reactor(Richard L. Moore)
Multigroup Diffusion Calculation of k_∞ for D₂O Lattices(N. Tralli, J. Agresta, W. Seibyl)
Corrosion of Irradiated Uranium Alloys(Sherman Greenberg)
Measurements of the Transport Mean Free Path of Thermal Neutrons in Beryllium as a Function of Temperature(G. deSaussure, E. G. Silver)
A New Approximate Treatment of the Energy-Dependent Boltzmann Equation(C. Raymond Mullin)
The Age of Plutonium-Beryllium Neutrons in Light Water(Frank A. Valente, Robert E. Sullivan)
Effective Resonance Integral for Uranium Carbide(Russel Vernon)
ANS News

Nonlinear Treatment of Large Perturbation in Power Reactor Stability

H. A. Sandmeier

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 85-92

Technical Paper / dx.doi.org/10.13182/NSE59-A25637

Relative Control Rod Worths of Some Rare Earth Oxides

Hugh F. Johnston, John L. Russell, Jr., Walter L. Silvernail

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 93-96

Technical Paper / dx.doi.org/10.13182/NSE59-A25638

Distribution and Elution of Fission Products upon ThO₂-UO₃ Slurry at Simulated Reactor Conditions

A. R. Fritsch, B. Levy

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 97-99

Technical Paper / dx.doi.org/10.13182/NSE59-A25639

Heavy Nuclide Cross Sections of Particular Interest to Thermal Reactor Operation: Conventions, Measurements and Preferred Values

R. W. Stoughton, J. Halperin

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 100-118

Technical Paper / dx.doi.org/10.13182/NSE59-A25640

Epithermal Hafnium Parameters for the Calculation of Control Rod Worth in Thermal Reactors

T. F. Ruane, M. L. Storm

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 119-127

Technical Paper / dx.doi.org/10.13182/NSE59-A25641

Neutron Thermalization Calculations for a Heterogeneous Lattice Containing Uranium and Plutonium Fuel in Water

P. Greebler, W. Harker, J. Harriman

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 128-134

Technical Paper / dx.doi.org/10.13182/NSE59-A25642

Variational Calculation of Control Rod Reactivity

Elias P. Gyftopoulos, Luis de Sobrino

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 135-139

Technical Paper / dx.doi.org/10.13182/NSE59-A25643

Permissible Voids in Photon Shields

D. G. Chappell

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 140-146

Technical Paper / dx.doi.org/10.13182/NSE59-A25644

Two-Group Albedo Theory and Application to Temperature Coefficient Calculations

Alan Jacobs

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 147-151

Technical Paper / dx.doi.org/10.13182/NSE59-A25645

On Control of Reactor Shut-down Involving Minimal Xenon Poisoning

Milton Ash, Richard Bellman, Robert Kalaba

Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 152-156

Technical Paper / dx.doi.org/10.13182/NSE59-A25646

Number 3

Table of Contents
Comments on Bell's Approximation to the Resonance Integral(Charles Kelber, Phillip Kier)
Solution Of The P₃ Equations In One and Two Dimensions(J. Davis, E. Gelbard, J. Pearson)
Fission Counter Sample Disk Holder and Slide(C. L. Truman)
On the Use of Dimensionless Variables in Reactor Kinetics(Gilbert B. Melese)

Enriched Boron-Titanium Dispersions

L. B. Prus, E. S. Byron, F. O. Von Plinsky, S. W. Porembka

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 167-173

Technical Paper / dx.doi.org/10.13182/NSE59-A25656

Blackness Theory and Coefficients for Slab Geometry

C. W. Maynard

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 174-186

Technical Paper / dx.doi.org/10.13182/NSE59-A25657

Nuclear Safety of Iron-Encased Fuel Elements

Norman Ketzlach

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 187-190

Technical Paper / dx.doi.org/10.13182/NSE59-A25658

Perturbation Methods for Reactor Diffusion Equations

Lowell H. Holway, Jr.

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 191-201

Technical Paper / dx.doi.org/10.13182/NSE59-A25659

Uniformly Spaced Control Elements in a Reactor: Theoretical Basis of Application of “Absorption Area” to Reactor Control Evaluation

Lewi Tonks

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 202-213

Technical Paper / dx.doi.org/10.13182/NSE59-A25660

The Elastic Response to Internal Blast Loading of Models of Outer Containment Structures for Nuclear Reactors

J. W. Hanna, W. O. Ewing, Jr. W. E. Baker

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 214-221

Technical Paper / dx.doi.org/10.13182/NSE59-A25661

Some Properties of Uranium-Fissium Alloys

S. T. Zegler M. V. Nevitt

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 222-228

Technical Paper / dx.doi.org/10.13182/NSE59-A25662

Minimum Total Mass

J. Ernest Wilkins, Jr.

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 229-232

Technical Paper / dx.doi.org/10.13182/NSE59-A25663

Determination of Time Behavior of Neutron Density and of Reactivity on the Argonaut Reactor

W. R. Kimel, W. E. Carey, F. G. Prohammer, G. C. Baldwin

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 233-237

Technical Paper / dx.doi.org/10.13182/NSE59-A25664

Analysis of the Coolant Expansion Due to a Loss-of-Coolant Accident in a Pressurized Water, Nuclear Power Plant

Tedric A. Harris

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 238-244

Technical Paper / dx.doi.org/10.13182/NSE59-A25665

Local Pressure Gradients in Forced Convection Vaporization

V. E. Schrock, L. M. Grossman

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE59-A25666

Number 4

Table of Contents

Transient Behavior of TRIGA, a Zirconium-Hydride, Water-Moderated Reactor

Richard Stone, H. P. Sleeper, J. R., Ralph, H. Stahl, Gordon West

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 255-259

Technical Paper / dx.doi.org/10.13182/NSE59-A28840

Polynomial Approximations in Neutron Transport Theory

W. R. Conkie

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 260-266

Technical Paper / dx.doi.org/10.13182/NSE59-A28841

An Iterative Method in Neutron Transport Theory

W. R. Conkie

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 267-271

Technical Paper / dx.doi.org/10.13182/NSE59-A28842

An Efficient Counting System for the Detection of Neutrons from Low-Yield Pulsed Neutron Sources

Lawrence Ruby, Joseph Bechen

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 272-278

Technical Paper / dx.doi.org/10.13182/NSE59-A28843

A Fuel Element for an Elevated-Temperature Critical Assembly

Carl E. Walter

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 279-283

Technical Paper / dx.doi.org/10.13182/NSE59-A28844

Errors in Reactivity Measurements Due to Photoneutron Effects

Charles Erwin Cohn

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 284-287

Technical Paper / dx.doi.org/10.13182/NSE59-A28845

A Monte Carlo Calculation of Thermal Utilization

A. Rotenberg, A. Lapidus, E. Wetherwell

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 288-293

Technical Paper / dx.doi.org/10.13182/NSE59-A28846

Flux Perturbation Produced by Ion Chambers and Fission Chambers

Alain Scola, William Managan

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 294-297

Technical Paper / dx.doi.org/10.13182/NSE59-A28847

Calculations of Flux Distributions in a Boiling Water Reactor

Y. Fukai, A. Shimizu, S. Miyamoto

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 298-305

Technical Paper / dx.doi.org/10.13182/NSE59-A28848

Flow Coastdown in a Loop After Pumping Power Cutoff

David Burgreen

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 306-312

Technical Paper / dx.doi.org/10.13182/NSE59-A28849

The Time-Dependent Thermal Neutron Flux from a Pulsed Subcritical Assembly

Stanley C. Fultz

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 313-319

Technical Paper / dx.doi.org/10.13182/NSE59-A28850

Kinetics of a Reactor Composed of Two Loosely Coupled Cores

G. C. Baldwin

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 320-327

Technical Paper / dx.doi.org/10.13182/NSE59-A28851

Measuring the Release Time and Total Drop Time of a Control Rod

Charles Zucker, Lewis Haring

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 328-332

Technical Paper / dx.doi.org/10.13182/NSE59-A28852

The Fluorination of Plutonium Tetrafluoride and Plutonium Dioxide by Fluorine

M. J. Steindler, D. V. Steidl, R. K. Steunenberg

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 333-340

Technical Paper / dx.doi.org/10.13182/NSE59-A28853

The Application of Topological Methods to the Kinetics of Homogeneous Reactors

Henri B. Smets, Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 341-349

Technical Paper / dx.doi.org/10.13182/NSE59-A28854

On the Removal of Volatile Fission Products from Uranium-Bismuth Reactor Fuels

Orrington E. Dwyer, Allen M. Eshaya

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 350-360

Technical Paper / dx.doi.org/10.13182/NSE59-A28855

Number 5

Table of Contents
Space and Energy Separability of Thermal Flux in a Diffusing Medium(E. M. Gelbard, J. J. Pearson)
Validity of the B_l Method for Fuel Cycle Analysis(S. A. Hasnain, Raymond L. Murray)
Age in D₂O-H₂O Mixtures(W. H. Arnold, Jr.)
The Slowing-Down Spectrum in a Heterogeneous Reactor(C. B. Bigham, R. M. Pearce)
Some Studies of Aqueous Uranium Oxide Slurries(Robert S. Hansen, Robert E. Minturn, Bert H. Clampitt)

Clad Titanium-Base Dispersions Containing Boron

E. S. Byron, F. O. VonPlinsky, S. W. Porembka

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 361-370

Technical Paper / dx.doi.org/10.13182/NSE59-A25672

Heat Transfer to Bingham Plastics in Laminar Flow through Circular Tubes with Internal Heat Generation

R. S. Schechter, E. H. Wissler

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 371-375

Technical Paper / dx.doi.org/10.13182/NSE59-A25673

Reactivity Associated with the Decay of Np²³⁹ in Irradiated Natural Uranium Dioxide

S. B. Gunst

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 376-378

Technical Paper / dx.doi.org/10.13182/NSE59-A25674

The Temperature Dependence of the Fission Cross Sections of Pu²³⁹, U²³⁵, and U²³³

C. B. Bigham

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 379-385

Technical Paper / dx.doi.org/10.13182/NSE59-A25675

Analytic Solutions for Transient Temperature Distributions in Two-Region Nuclear Reactor Fuel Elements

Francis Narin, David Langford

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 386-390

Technical Paper / dx.doi.org/10.13182/NSE59-A25676

Properties of Uranium Monocarbide

C. A. Smith, Frank Rough

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 391-395

Technical Paper / dx.doi.org/10.13182/NSE59-A25677

New Shielding Materials for High-Temperature Application

H. E. Hungerford, R. F. Mantey, L. P. Van Maele

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 396-408

Technical Paper / dx.doi.org/10.13182/NSE59-A25678

Simplified Simulation of a Boiling Water Reactor Power Plant

Robley E. George, Alexander Sesonske

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 409-413

Technical Paper / dx.doi.org/10.13182/NSE59-A25679

Autocorrelation Functions of Counting Rate in Nuclear Reactors

Carlos Vélez

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 414-419

Technical Paper / dx.doi.org/10.13182/NSE59-A25680

New Ideas for Nuclear Reactors

Eugene P. Wigner

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 420-432

Technical Paper / dx.doi.org/10.13182/NSE59-A25681

A Precise Determination of the Total Cross Section of Uranium-235 from 0.000818 ev to 0.0818 ev

G. J. Safford, W. W. Havens, Jr., B. M. Rustad

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 433-440

Technical Paper / dx.doi.org/10.13182/NSE59-A25682

Effective Cadmium Cutoff Energies

R. W. Stoughton, J. Halperin, Marjorie P. Lietzke

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 441-447

Technical Paper / dx.doi.org/10.13182/NSE59-A25683

The Power Noise Transfer Function of a Reactor

M. N. Moore

Nuclear Science and Engineering / Volume 6 / Number 5 / November 1959 / Pages 448-452

Technical Paper / dx.doi.org/10.13182/NSE59-A25684

Number 6

Table of Contents

Analysis of the Zero Power Reactor Transfer Function

H. C. Corben

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 461-465

dx.doi.org/10.13182/NSE59-A15503

Neutron Spectra Measurements

R. S. Stone, R. E. Slovacek

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 466-474

dx.doi.org/10.13182/NSE59-A15504

Complete Spherical Harmonics Solution of the Boltzmann Equation for Neutron Transport in Homogeneous Media with Cylindrical Geometry

Walter Kofink

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 475-486

dx.doi.org/10.13182/NSE59-A15505

Fission Fragment Impact Trapping by ThO₂ Slurry Particles

Donald G. Gardner

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 487-492

dx.doi.org/10.13182/NSE59-A15506

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. I. Introduction

L. Burris, H. M. Feder, S. Lawroski, W. A. Rodger, R. C. Vogel

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 493-495

dx.doi.org/10.13182/NSE59-A15507

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. II. Experimental Furnaces

G. J. Bernstein, G. A. Bennett, N. R. Chellew, V. G. Trice, Jr.

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 496-500

dx.doi.org/10.13182/NSE59-A15508

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. III. Preparation of Experimental Alloys

D. C. Hampson, G. A. Bennett, N. R. Chellew

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 501-503

dx.doi.org/10.13182/NSE59-A15509

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. IV. Interaction of Uranium and Its Alloys with Refractory Oxides

C. L. Rosen, N. R. Chellew, H. M. Feder

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 504-510

dx.doi.org/10.13182/NSE59-A15510

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. V. Yield of Fissionable Material upon Pouring

G. A. Bennett, N. R. Chellew, D. C. Hampson

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 511-513

dx.doi.org/10.13182/NSE59-A15511

An Iteration Method for the Specification of Multigroup Bucklings

A. Foderaro

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 514-524

dx.doi.org/10.13182/NSE59-A15512

The Shielding of Helical Ducts

C. C. Horton

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 525-529

dx.doi.org/10.13182/NSE59-A15513

Material Buckling Measurements in a Subcritical Assembly

Robert E. Uhrig

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 530-532

dx.doi.org/10.13182/NSE59-A15514

Low Decontamination Reprocessing of Thorium-Uranium Alloys by Induction Drip Melting

F. W. Dodge, E. W. Murbach, L. A. Hanson

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 533-536

dx.doi.org/10.13182/NSE59-A15515

Breeding Potential of Thermal Reactors

J. Chernick, S. Oleksa Moore

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 537-544

dx.doi.org/10.13182/NSE59-A15516

Interpretation of Thermal Neutron Mean Lifetime Experiments

Fred Holzer, Marshall F. Crouch

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 545-553

dx.doi.org/10.13182/NSE59-A15517