Home / Publications / Journals / Nuclear Science and Engineering / Volume 5

Volume 5

Number 1

Table of Contents
Heating of Positive Ions in a Thermonuclear Plasma(H. M. Mott-Smith)
Average Flux In Reactor Test Volumes(Raymond L. Murray, Gerald H. Katzin, Alfred L. Mowery, Jr)
Optimum Control and Flat Flux(A. Sauer)
ANS News(Octave J. Du Temple)

Resonance Escape Probability in Hydrogenous Lattices

W. W. Clendenin

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 1-4

Technical Paper / dx.doi.org/10.13182/NSE59-A27320

Perturbation Theory of Control Elements. II

Bertram Wolfe, David Fischer

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 5-10

Technical Paper / dx.doi.org/10.13182/NSE59-A27321

The Utilization of a Cold Trap to Stabilize Suspensions of UO₂ in NaK

P. R. Huebotter, W. R. Seitz

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 11-14

Technical Paper / dx.doi.org/10.13182/NSE59-A27322

Effect of Radiation on Corrosion of Structural Materials by Molten Fluorides

G. W. Keilholtz, J. G. Morgan, W. E. Browning

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 15-20

Technical Paper / dx.doi.org/10.13182/NSE59-A27323

Theory of Pulsed Neutron Experiments in Multiplying Media

T. J. Krieger, P. F. Zweifel

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 21-27

Technical Paper / dx.doi.org/10.13182/NSE59-A27324

Nuclear Radiation Heating: Preliminary Design Considerations

Barney L. Byrum, John A. Biggerstaff

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 28-31

Technical Paper / dx.doi.org/10.13182/NSE59-A27325

The Width of the 1 ev Resonance in Plutonium-240

B. R. Leonard, Jr., E. J. Seppi, W. J. Friesen

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 32-35

Technical Paper / dx.doi.org/10.13182/NSE59-A27326

Iterative Solutions to the P₁ and Double-P¹ Equations₁

E. Gelbard, J. Davis, J. Pearson

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 36-44

Technical Paper / dx.doi.org/10.13182/NSE59-A27327

Intermediate Energy Neutron Leakage Through Iron

D. E. Wood

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 45-48

Technical Paper / dx.doi.org/10.13182/NSE59-A27328

Comparison of the Average Number of Prompt Neutrons Emitted in the Fission of U²³³, U²³⁵, Pu²³⁹, and Pu²⁴¹

G. de Saussure, E. G. Silver

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 49-54

Technical Paper / dx.doi.org/10.13182/NSE59-A27329

Half Lives of N¹⁶, Mg²⁷, Al²⁸, S³⁷, and Rh^104m₂

J. O. Elliot, F. C. Young

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 55-56

Technical Paper / dx.doi.org/10.13182/NSE59-A27330

Calculation of Thermal Utilization in Heterogeneous Nuclear Reactors by the P₃ Spherical Harmonics Approximation

T. Asaoka

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 57-60

Technical Paper / dx.doi.org/10.13182/NSE59-A27331

Fast Fission Effect in Lattices of Natural Uranium and Heavy Water

A. H. Futch, Jr.

Nuclear Science and Engineering / Volume 5 / Number 1 / January 1959 / Pages 61-67

Technical Paper / dx.doi.org/10.13182/NSE59-A27332

Number 2

Table of Contents
Space-Time Burnout of an Absorbing Slab(W. H. Arnold, Jr)
Concerning the Theory of Control Sheets(H. S. Wilf)
A Simple Treatment for Effective Resonance Absorption Cross Sections in Dense Lattices(George I. Bell)
ANS News(Octave J. Du Temple)

A Simple Analytical Formulation of the Dancoff Correction

J. A. Thie

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 75-77

Technical Paper / dx.doi.org/10.13182/NSE59-A25559

A Kinetic Study of Irradiation Induced Phase Changes in Uranium-9 w/o Molybdenum Alloy¹

M. L. Bleiberg

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 78-87

Technical Paper / dx.doi.org/10.13182/NSE59-A25560

Sources of Error in Reactivity Determinations by Means of Asymptotic Period Measurements¹

B. J. Toppel

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 88-98

Technical Paper / dx.doi.org/10.13182/NSE59-A25561

Inelastic Scattering of Cold Neutrons from Several Hydrogenous Liquids¹

R. M. Brugger, L. W. McClellan, G. B. Streetman, J. E. Evans

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 99-104

Technical Paper / dx.doi.org/10.13182/NSE59-A25562

Plutonium Recycle in the Calder Hall Type Reactor

Louis J. Barbieri, J. Wallace Webster, Ken Tang Chow

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 105-119

Technical Paper / dx.doi.org/10.13182/NSE59-A25563

Operating Characteristics of a Graphite-Moderated Subcritical Assembly

Robert E. Uhrig

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 120-126

Technical Paper / dx.doi.org/10.13182/NSE59-A25564

The Computation of Excess Reactivity From Power Traces

H. C. Corben

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 127-131

Technical Paper / dx.doi.org/10.13182/NSE59-A25565

Period-Reactivity Relations Determined Directly From Prompt-Burst Neutron Decay Data

G. R. Keepin

Nuclear Science and Engineering / Volume 5 / Number 2 / February 1959 / Pages 132-136

Technical Paper / dx.doi.org/10.13182/NSE59-A25566

Number 3

Table of Contents
Elastic Constants of Polycrystalline Uranium(HENRY L. LAQUER)
Attenuation of 14-Mev Neutrons in Water and in 6-In. Lead and Water(V. P. Duggal, S. M. Puri, K. Sri Ram)
The Inertia Transient in Reactor Draining(David Burgreen)
Plastic Bending of Rods or Tubes with Radial Temperature Distributions(K. R. Merckx)
Note on the Thermal Neutron Spectrum in a Diffusing Medium(G. De Coulon, P. F. Zweifel)
ANS News(Octave J. Du Temple)

Zeta Potentials of ThO₂ and of Stainless Steel as Related to Aggregation and Caking

B. Levy, A. R. Fritsch

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 143-149

Technical Paper / dx.doi.org/10.13182/NSE59-A25572

Evaluation of a Bank of Slab-type Control Rods

Robert W. Deutsch

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 150-155

Technical Paper / dx.doi.org/10.13182/NSE59-A25573

Calculated Activities and Abundances of U²³⁵ Fission Products

R. C. Bolles, N. E. Ballou

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 156-185

Technical Paper / dx.doi.org/10.13182/NSE59-A25574

Time Constant of Cylindrical Fuel Pin with Axial Coolant Flow

H. A. Sandmeier, D. M. O’Shea

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 186-189

Technical Paper / dx.doi.org/10.13182/NSE59-A25575

Restricted Minimum Critical Mass

J. Devooght

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 190-194

Technical Paper / dx.doi.org/10.13182/NSE59-A25576

A Note on the Elastic Constants of Uranium

S. J. Rothman, E. S. Fisher

Nuclear Science and Engineering / Volume 5 / Number 3 / March 1959 / Pages 195-196

Technical Paper / dx.doi.org/10.13182/NSE59-A25577

Number 4

The Behavior of a Reactor at Prompt Critical when the Reactivity is a Linear Function of Time

J. Ernest Wilkins, Jr.

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 207-214

Technical Paper / dx.doi.org/10.13182/NSE59-A25585

Thermal Buckling of Cruciform Control Rods

John E. Goldberg, M. F. Sankovich

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 215-218

Technical Paper / dx.doi.org/10.13182/NSE59-A25586

Magnesium-Clad Wedge S-Shaped Fuel Plates for Gas-Cooled Reactors

Guy H. Cannon

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 219-224

Technical Paper / dx.doi.org/10.13182/NSE59-A25587

Pile Oscillator Measurements of Eta

C. O. Muehlhause

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 225-226

Technical Paper / dx.doi.org/10.13182/NSE59-A25588

A UO₂—Liquid Metal Slurry Reactor for Economic Power

J. K. Davidson, W. L. Robb, O. N. Salmon, J. B. Sampson

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 227-236

Technical Paper / dx.doi.org/10.13182/NSE59-A25589

Resonance Escape Probability in Water Lattice

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 237-241

Technical Paper / dx.doi.org/10.13182/NSE59-A25590

A Method of Correlating Burnout Heat Flux Data

G. Sonnemann

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 242-247

Technical Paper / dx.doi.org/10.13182/NSE59-A25591

On the Validity of the Second Fundamental Theorem for Small Reactors

Erdal Inönü

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 248-253

Technical Paper / dx.doi.org/10.13182/NSE59-A25592

The Dynamic Reactivity Interpretation of Pulsed Neutron Measurements

B. E. Simmons

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 254-256

Technical Paper / dx.doi.org/10.13182/NSE59-A25593

A Study of Split Cores for Research Reactors

F. E. Jablonski, R. S. Carter

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 257-263

Technical Paper / dx.doi.org/10.13182/NSE59-A25594

Pile Neutron Capture Cross Sections of Np²³⁹

E. M. Kinderman, H. W. Lefevre, H. H. Van Tuyl

Nuclear Science and Engineering / Volume 5 / Number 4 / April 1959 / Pages 264-268

Technical Paper / dx.doi.org/10.13182/NSE59-A25595

Number 5

On the Termination of Reactor Excursions

John Macphee

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 273-284

Technical Paper / dx.doi.org/10.13182/NSE59-A25599

A Simple Device for Personnel Monitoring of an Accidental Nuclear Reaction

H. F. Henry, J. C. Bailey, R. C. Rohr

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 285-290

Technical Paper / dx.doi.org/10.13182/NSE59-A25600

Reduced Delayed Neutron Group Representations

R. E. Skinner, E. R. Cohen

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 291-298

Technical Paper / dx.doi.org/10.13182/NSE59-A25601

Thermal Activation Shapes in a Water-Moderated Critical Assembly

M. Goldsmith, T. M. Ryan

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 299-305

Technical Paper / dx.doi.org/10.13182/NSE59-A25602

The Transmission of Neutrons in Multilayered Slab Geometry

Herbert S. Wilf

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 306-319

Technical Paper / dx.doi.org/10.13182/NSE59-A25603

Measurement of the Doppler Temperature Effect in an EBR-I Type Assembly

W. Y. Kato, D. K. Butler

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 320-330

Technical Paper / dx.doi.org/10.13182/NSE59-A25604

Determination of Reactor Kinetic Parameters by Pile Noise Analysis

Charles Erwin Cohn

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 331-335

Technical Paper / dx.doi.org/10.13182/NSE59-A25605

The Number of Elastic Collisions in a Finite Lethargy Interval

Wendell C. Demarcus

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 336-337

Technical Paper / dx.doi.org/10.13182/NSE59-A25606

The Thermal Neutron Spectrum in a Heterogeneous Reactor

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 5 / Number 5 / May 1959 / Pages 338-346

Technical Paper / dx.doi.org/10.13182/NSE59-A25607

Number 6

Nucleate Boiling Characteristics of Organic Reactor Coolants

D. P. Jordan G. Leppert

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 349-359

Technical Paper / dx.doi.org/10.13182/NSE59-A25610

Two Region Studies in Slightly Enriched Water-Moderated Uranium and Uranium Dioxide Lattices

John J. Volpe, George G. Smith, Daniel Klein, F. S. Frantz, Jocelyn C. Andrews

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 360-370

Technical Paper / dx.doi.org/10.13182/NSE59-A25611

A Monte Carlo Method for Criticality Problems

W. Goad, R. Johnston

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

Technical Paper / dx.doi.org/10.13182/NSE59-1

Analysis of Reactor Oscillations for Coefficients of Reactivity

H. Dean Brown, William E. Loewe

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 376-381

Technical Paper / dx.doi.org/10.13182/NSE59-A25613

The Use of Thermally Black Control Sheets

R. J. Mcwhorter, John Russell, Bertram Wolfe

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 382-389

Technical Paper / dx.doi.org/10.13182/NSE59-A25614

Turbulent Liquid-Metal Heat Transfer in Channels

H. F. Poppendiek

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 390-404

Technical Paper / dx.doi.org/10.13182/NSE59-A25615

Transfer Functions of Distributed Parameter Nuclear Reactor Systems

Elias P. Gyftopoulos, Henry B. Smets

Nuclear Science and Engineering / Volume 5 / Number 6 / June 1959 / Pages 405-414

Technical Paper / dx.doi.org/10.13182/NSE59-A25616