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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE59-A27332

Number 2

Table of Contents
Concerning the Theory of Control Sheets (H. S. Wilf)
Space-Time Burnout of an Absorbing Slab (W. H. Arnold, Jr)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE59-A25616