Home / Publications / Journals / Nuclear Science and Engineering / Volume 7

Volume 7

Number 1

Table of Contents

Reactivity Effects of Large Voids in the Reflector of a Light-Water-Moderated and -Reflected Reactor

A. B. Reynolds, T. J. Thompson, K. M. Henry, E. B. Johnson

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE60-A25691

The Slowing Down of Neutrons by Deuterium

M. M. Levine, K. E. Roach, D. B. Wehmeyer, P. F. Zweifel

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 14-20

Technical Paper / dx.doi.org/10.13182/NSE60-A25692

Steels for Nuclear Reactors

H. F. Beeghly

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 21-25

Technical Paper / dx.doi.org/10.13182/NSE60-A25693

An Accurate Transfer Function for the Dynamic Analysis of Temperature and Heat Release in Cylindrical Fuel Elements

Modesto Iriarte, Jr.

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 26-32

Technical Paper / dx.doi.org/10.13182/NSE60-A25694

Approximate Solutions of the Reactor Kinetic Equations for Ramp Inputs

John MacPhee

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 33-43

Technical Paper / dx.doi.org/10.13182/NSE60-A25695

Enriched-Uranium Hydride Critical Assemblies

G. A. Linenberger, J. D. Orndoff, H. C. Paxton

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 44-57

Technical Paper / dx.doi.org/10.13182/NSE60-A25696

Integral Transport Theory of Thermal Utilization Factor in Infinite Slab Geometry

Michel H. Theys

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 58-63

Technical Paper / dx.doi.org/10.13182/NSE60-A25697

Space-Dependent Prompt Kinetics of a Subcritical Reactor

Joseph Agresta, Lyle B. Borst

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 64-68

Technical Paper / dx.doi.org/10.13182/NSE60-A25698

An Approximate Method for Treating Neutron Slowing Down

Gerald Goertzel, Eugene Greuling

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 69-72

Technical Paper / dx.doi.org/10.13182/NSE60-A25699

OMR Flat Plate Fuel Element Fabrication

G. V. Alm, E. E. Garrett, M. H. Binstock

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 73-82

Technical Paper / dx.doi.org/10.13182/NSE60-A25700

Development of Centrifugal Pumps for Operation with Liquid Metals and Molten Salts at 1100–1500°F

A. G. Grindell, W. F. Boudreau, H. W. Savage

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 83-91

Technical Paper / dx.doi.org/10.13182/NSE60-A25701

Number 2

Table of Contents

Effects of the Contamination by Light Water on Lattices of Natural Uranium Rods in Heavy Water

Bernard S. Finn, James W. Wade

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 93-96

Technical Paper / dx.doi.org/10.13182/NSE60-A29076

Thermal Stresses in Nuclear Reactor Vessel Nozzles

J. S. Busch, A. J. Martenson, S. W. Sinderson, C. F. Peck, Jr.

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 97-103

Technical Paper / dx.doi.org/10.13182/NSE60-A29077

Accuracy of the S_n Code in Cell Calculations

A. V. Campise

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 104-110

Technical Paper / dx.doi.org/10.13182/NSE60-A29078

Irradiation of Uranium Monocarbide

F. A. Rough, A. W. Hare, R. B. Price, S. Alfant

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 111-121

Technical Paper / dx.doi.org/10.13182/NSE60-A29079

The Use of the Generation Time in Reactor Kinetics

Jeffery Lewins

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 122-126

Technical Paper / dx.doi.org/10.13182/NSE60-A29080

Convergence of the S_n Method for Thermal Systems

E. Blue, H. P. Flatt

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 127-132

Technical Paper / dx.doi.org/10.13182/NSE60-A29081

Feasibility of Radioactive Waste Disposal in Shallow Sedimentary Formations

J. Wade Watkins, F. E. Armstrong, R. J. Heemstra

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 133-143

Technical Paper / dx.doi.org/10.13182/NSE60-A29082

Greuling-Goertzel Calculations in Heavy Water

R. J. Mack, P. F. Zweifel

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 144-146

Technical Paper / dx.doi.org/10.13182/NSE60-A29083

A Wide-Range Neutron Detector and Monitoring Instrument

Karl G. A. Porges, Thomas E. Klippert

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 147-155

Technical Paper / dx.doi.org/10.13182/NSE60-A29084

Statistical Analysis of Hot Channel Factors

P. A. Rude, A. C. Nelson, Jr.

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 156-161

Technical Paper / dx.doi.org/10.13182/NSE60-A29085

Collision Probabilities and Resonance Integrals for Lattices

Wolfgang Rothenstein

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 162-171

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Many-fold Moment Method

D. Schiff, S. Ziering

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 172-183

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The Absorption Cross Section of Copper for Thermal Neutrons

D. J. Donahue, R. A. Bennett, D. D. Lanning

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 184-186

Technical Paper / dx.doi.org/10.13182/NSE60-A29088

Total Neutron Cross Sections of U²³³ and U²³⁵ from 0.02 to 0.08 ev

O. D. Simpson, M. S. Moore, F. B. Simpson

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 187-192

Technical Paper / dx.doi.org/10.13182/NSE60-A29089

Total Cross Sections of Ti, V, Y, Ta, and W

R. E. Schmunk, P. D. Randolph, R. M. Brugger

Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 193-197

Technical Paper / dx.doi.org/10.13182/NSE60-A29090

Number 3

Table of Contents
A Method for Interpolation in Moderator to Fuel Ratio Dependent Bucklings(J. Thie)
Delayed Neutron Effects During Flux Tilt Transients(S. Kaplan, S. G. Margolis)
Analysis of Neutron Flux Data for Accurate Determination of Relaxation Length(Leo Seren, Denis Tsakarissianos)

Measurement of Air Blast Effects from Simulated Nuclear Reactor Core Excursions

Wendell C. Olson, Richard J. Larson, Harry Goldstein

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 199-209

Technical Paper / dx.doi.org/10.13182/NSE60-A25703

The Decay of a Thermalized Neutron Pulse

Mark Nelkin

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 210-216

Technical Paper / dx.doi.org/10.13182/NSE60-A25704

Methods and Cross Sections for Calculating the Fast Effect

Morton R. Fleishman, Harry Soodak

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 217-227

Technical Paper / dx.doi.org/10.13182/NSE60-A25705

Neutron Absorption by Control Rods of Varying Transparency

H. Überall

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 228-234

Technical Paper / dx.doi.org/10.13182/NSE60-A25706

A Useful Analogy for Single-Group Neutron Diffusion Theory

James R. Melcher

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 235-239

Technical Paper / dx.doi.org/10.13182/NSE60-A25707

Slowing Down of Neutrons in Graphite Close to Thermal Equilibrium

L. S. Kothari, P. G. Khubchandani

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 240-244

Technical Paper / dx.doi.org/10.13182/NSE60-A25708

Correlation of Burnout Heat-Flux Data at 2000 psia

Donald W. Bell

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 245-251

Technical Paper / dx.doi.org/10.13182/NSE60-A25709

Calculation of the Effective Resonance Integral of U²³⁸

A. R. Vernon

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 252-259

Technical Paper / dx.doi.org/10.13182/NSE60-A25710

Comparison Theorems for the Estimation of Average Collision Probabilities. II

Lawrence Dresner

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 260-262

Technical Paper / dx.doi.org/10.13182/NSE60-A25711

Experimental Check of a Monte Carlo-Calculated Distribution of Resonance Neutron Capture in a Gold Rod

Judson Hardy, Jr., G. G. Smith, D. Klein

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 263-267

Technical Paper / dx.doi.org/10.13182/NSE60-A25712

The Time-Dependent Importance of Neutrons and Precursors

Jeffery Lewins

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 268-274

Technical Paper / dx.doi.org/10.13182/NSE60-A25713

Number 4

Table of Contents
On the Fast Effect in Beryllium(P. G. Aline, P. E. Novak, B. Wolfe)

Static and Dynamic Multiplication Factors and Their Relation to the Inhour Equation

E. E. Gross, J. H. Marable

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 281-291

Technical Paper / dx.doi.org/10.13182/NSE60-A25718

Slowing Down of Neutrons

T. Teichmann

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 292-294

Technical Paper / dx.doi.org/10.13182/NSE60-A25719

Velocity Dependent Neutron Transport Theory

W. R. Conkie

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 295-303

Technical Paper / dx.doi.org/10.13182/NSE60-A25720

On the Theory of the Diffusion Cooling Effect in Homogeneous and Heterogeneous Assemblies

W. Häfele, L. Dresner

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 304-312

Technical Paper / dx.doi.org/10.13182/NSE60-A25721

Transient Piston Ring Wear in Automotive Engines Using Fe⁵⁹

James J. Gumbleton, Farno L. Green, William J. Mayer

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 313-319

Technical Paper / dx.doi.org/10.13182/NSE60-A25722

Continuous Counting of Gamma Rays from Hot Radioactive Liquids

Farno L. Green, A. Somerville

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 320-322

Technical Paper / dx.doi.org/10.13182/NSE60-A25723

Isolation of Carrier-Free Mn⁵⁴ and I¹²⁵ from Cyclotron Targets

H. T. Russell

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 323-324

Technical Paper / dx.doi.org/10.13182/NSE60-A25724

Cyclotron Targets Using Enriched Stable Isotopes

P. S. Baker, F. R. Duncan, L. O. Love

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 325-326

Technical Paper / dx.doi.org/10.13182/NSE60-A25725

The Fission Gas Problem for Mobile Fuel Fast Reactors

Frederick G. Hammitt, Evan C. Kovacic, Frederick J. Leitz

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 327-335

Technical Paper / dx.doi.org/10.13182/NSE60-A25726

An Analysis of Neutron Flux Spatial Oscillation Due to Xenon Build-Up in a Large Power Reactor Core

Keiichi Mochizuki, Atushi Takeda

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 336-344

Technical Paper / dx.doi.org/10.13182/NSE60-A25727

Thermal Neutron Flux Spectrum in a Medium with a Temperature Discontinuity

D. A. Kottwitz

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 345-354

Technical Paper / dx.doi.org/10.13182/NSE60-A25728

Neutron Energy Spectrum Measurements in Unmoderated Assemblies

G. J. Fischer

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 355-362

Technical Paper / dx.doi.org/10.13182/NSE60-A25729

Diffusion of Intermediate Energy Neutrons into a Thick Resonance Absorber

H. H. Hummel, D. Meneghetti

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 363-368

Technical Paper / dx.doi.org/10.13182/NSE60-A25730

Relationships between Reactivity Changes, Buckling Changes, and Periods in a Heavy Water Reactor

B. S. Finn

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 369-376

Technical Paper / dx.doi.org/10.13182/NSE60-A25731

Considerations in the Design of a Nuclear Rocket

John J. Newgard, Myron M. Levoy

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 377-386

Technical Paper / dx.doi.org/10.13182/NSE60-A25732

Maximizing Production of Radioisotopes in a Cyclotron

Farno L. Green, John A. Martin

Nuclear Science and Engineering / Volume 7 / Number 4 / April 1960 / Pages 387-391

Technical Paper / dx.doi.org/10.13182/NSE60-A25733

Number 5

Table of Contents
A Note Concerning the Purely Proton Moderated Spectrum(B. J. Toppel)
Calibration of Lutetium for Measurements of Effective Neutron Temperatures(L. C. Schmid, W. P. Stinson)
Void Coefficient Measurement(Frederick J. Shon, Charles Zucker)
Dejacketing Pellets Using RF Heat(B. J. Massey)
γ — γ Coincidence Method for Measuring Resonance Escape Probability in U²³⁸ Lattices(Rudolph Sher)

Absorption Cross Section of Graphite

P. F. Nichols

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 395-399

Technical Paper / dx.doi.org/10.13182/NSE60-A25736

The Effects of Internal Heat Generation on Heat Transfer in Thin Fins

W. S. Minkler, W. T. Rouleau

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 400-406

Technical Paper / dx.doi.org/10.13182/NSE60-A25737

The Reactivity of Natural UO₂ Irradiated to 6 × 10²¹ n/cm²

S. B. Gunst, E. D. McGarry, J. J. Scoville

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 407-418

Technical Paper / dx.doi.org/10.13182/NSE60-A25738

On the Validity of the Second Fundamental Theorem in a Medium with Anisotropic Scattering

Lawrence Dresner

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 419-424

Technical Paper / dx.doi.org/10.13182/NSE60-A25739

Elastic-Plastic Thermal Stresses in Tubes Subjected to Uniform Heat Generation Evaluation of Experimental Results Obtained Using Graphite Tubes

T. Kammash

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 425-434

Technical Paper / dx.doi.org/10.13182/NSE60-A25740

An Investigation of Effective Neutron Temperatures

W. P. Stinson, L. C. Schmid, R. E. Heineman

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 435-441

Technical Paper / dx.doi.org/10.13182/NSE60-A25741

The Density of Liquid Lead and of Dilute Solutions of Nickel in Lead

S. W. Strauss, L. E. Richards, B. F. Brown

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 442-447

Technical Paper / dx.doi.org/10.13182/NSE60-A25742

Fission-to-Indium Age in Water

D. B. Lombard, C. H. Blakchard

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 448-453

Technical Paper / dx.doi.org/10.13182/NSE60-A25743

Resonance Capture of Neutrons in Nonheavy Absorbers

W. Rothenstein, J. Chernick

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 454-457

Technical Paper / dx.doi.org/10.13182/NSE60-A25744

Experimental Investigations of Pressure Drop through Interrupted-Plate-Type Fuel Elements

B. W. LeTourneau, R. E. Grimble

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 458-467

Technical Paper / dx.doi.org/10.13182/NSE60-A25745

On the Temperature Dependence of the Thermal Neutron Flux Kernel

D. C. Anderson

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 468-471

Technical Paper / dx.doi.org/10.13182/NSE60-A25746

A Simplified Theory of Pile Noise

Charles Erwin Cohn

Nuclear Science and Engineering / Volume 7 / Number 5 / May 1960 / Pages 472-475

Technical Paper / dx.doi.org/10.13182/NSE60-4

Number 6

Table of Contents
Milne's Problem for a Velocity-Dependent Mean Free Path(Mark Nelkin)
Volcanic Energy Resources(R. L. Macklin)
Criticality Study on TREAT Reactor-Cause of Excess Boron Impurity in Graphite(H. P. Iskenderian)
The Use of the Generation Time in Reactor Kinetics(Jeffery Lewins)

Surface Perturbation Theory

Jeffery Lewins

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 481-486

Technical Paper / dx.doi.org/10.13182/NSE60-A25754

Gas Bubble Formation in Irradiated Plastics and Reactor Fuels

G. G. Bentle

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 487-495

Technical Paper / dx.doi.org/10.13182/NSE60-A25755

Flat Flux by Nonuniform Moderation

Jack M. Ravets, John R. Lamarsh

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 496-501

Technical Paper / dx.doi.org/10.13182/NSE60-A25756

Parameters of the Lu¹⁷⁶ Neutron Resonance at 0.142 ev

Joseph P. Roberge, Vance L. Sailor

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 502-504

Technical Paper / dx.doi.org/10.13182/NSE60-A25757

The Black Void Reactor Concept

C. O. Muehlhause

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 505-507

Technical Paper / dx.doi.org/10.13182/NSE60-A25758

In-Pile Loop Study of UO₂-NaK Slurry

R. D. Carlson

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 508-513

Technical Paper / dx.doi.org/10.13182/NSE60-A25759

Measurements of Parameters Leading to P₂₈, f, and ϵ in Light Water Moderated 4.48% and 2.73% Enriched Lattices

Victor E. Grob, E. Santandrea, Hilmar Ritz

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 514-524

Technical Paper / dx.doi.org/10.13182/NSE60-A25760

The Prediction of Steam Volume Fractions in Boiling Systems

J. F. Marchaterre, M. Petrick

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 525-532

Technical Paper / dx.doi.org/10.13182/NSE60-A25761

Boundedness and Stability in Nonlinear Reactor Dynamics

Elias P. Gyftopoulos, Jacques Devooght

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 533-540

Technical Paper / dx.doi.org/10.13182/NSE60-A25762

An H₂O-D₂O Moderated Reactor

Norman P. Klug, P. F. Zweifel

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 541-544

Technical Paper / dx.doi.org/10.13182/NSE60-A25763

Breeding Ratio in U²³³ and Pu²³⁹ Fueled Reactors

Melvin M. Levine

Nuclear Science and Engineering / Volume 7 / Number 6 / June 1960 / Pages 545-551

Technical Paper / dx.doi.org/10.13182/NSE60-A25764