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Number 1

Table of Contents
A Criticism of the Use of Diffusion Theory for the Study of Thermal Neutrons in Beryllium (Paul Michael)
Comments on Michael's Criticism of the Use of Diffusion Theory for the Study of Thermal Neutrons in Beryllium (P. S. Grover, L. S. Kothari)
Reply to a Note by Jeffery Lewins and a Simplified Development of the Maximum Principle (John J. Roberts, Harold P. Smith, Jr.)
Assault (D. R Vondy, T. B. Fowler, M. L. Tobias)

Effects of Gamma Radiation on Cation-Exchange Resin in a Flowing-Water System
W. C. Yee, W. Davis, Jr.
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 1-5
Technical Paper | doi.org/10.13182/NSE66-A18118
Cadmium Cutoff Energies for Resonance Absorbers in Activation and Reactivity Measurements
H. L. Brown, Jr., T. J. Connolly
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 6-17
Technical Paper | doi.org/10.13182/NSE66-A18119
Resonance Absorption in Particles
R. A. Lewis and T. J. Connolly
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 18-25
Technical Paper | doi.org/10.13182/NSE66-A18120
The Ratio of ²³⁸ U Capture and ²³⁵U Fission Cross Sections in Fast Reactors
William G. Davey
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 26-41
Technical Paper | doi.org/10.13182/NSE66-A18121
Optimal Reflectors to Achieve Criticality
Martin S. Tierney, Paul Waltman
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 42-48
Technical Paper | doi.org/10.13182/NSE66-A18122
Integral Transport Theory
Adnan A. Aswad, G. R. Dalton
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 49-59
Technical Paper | doi.org/10.13182/NSE66-A18123
The Generalized First-Flight Collision Probability in the Cylindricalized Lattice System
Hiroshi Takahashi
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 60-71
Technical Paper | doi.org/10.13182/NSE66-A18124
Reactor-Kinetics Stability Criteria
Gerald S. Lellouche
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 72-76
Technical Paper | doi.org/10.13182/NSE66-A18125
Application of Dynamic Programming to Optimal Shutdown Control
M. Ash
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 77-86
Technical Paper | doi.org/10.13182/NSE66-A18126
The Thermal-Neutron-Activation Cross Section of ⁵⁹Co
R. Vaninbroukx
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 87-88
Technical Note | doi.org/10.13182/NSE66-A18127
Local Stability in Reactors with a Linear Feedback
A. Ziya Akcasu
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 88-89
Technical Note | doi.org/10.13182/NSE66-A18128
A Synthetic Kernel for a Heavy Species
Coleridge A. Wilkins
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 89-90
Technical Note | doi.org/10.13182/NSE66-A18129
On the Variation of the Lu:Dy Activation Ratio in Reactor Cells
J. Smit, R. J. J. Stamm'ler
Nuclear Science and Engineering | Volume 24 | Number 1 | January 1966 | Pages 90-92
Technical Note | doi.org/10.13182/NSE66-A18130

Number 2

Table of Contents
GAMLEG - A FORTRAN Code to Produce Multigroup Cross Sections for Photon Transport Calculations (K. D. Lathrop)
The Sorby Centennial Symposium On The History Of Metallurgy (William A. Mugde)
Nuclear Reactions Volume II (Herbert Goldstein)

Heat Transfer to Liquid Metals Flowing Turbulently in Eccentric Annuli—I
Wen-Shi Yu, Orrington E. Dwyer
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 105-117
Technical Paper | doi.org/10.13182/NSE66-A18295
An Aluminosilicate Ion Exchanger for Recovery and Transport of ₁₃₇Cs from Fission-Product Wastes
R. E. Lewis, T. A. Butler, E. Lamb
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 118-122
Technical Paper | doi.org/10.13182/NSE66-A18296
The Correlation Among Pore-Size Distribution, Permeability, and Diffusion in Graphite
J. Schlösser
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 123-132
Technical Paper | doi.org/10.13182/NSE66-A18297
Effect of Distribution of Fissile Material on Critical Mass
H. K. Clark
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 133-141
Technical Paper | doi.org/10.13182/NSE66-A18298
Atomic Motions in a Rigid Sphere Gas as a Problem in Neutron Transport
Rashmi C. Desai, Mark Nelkin
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 142-152
Technical Paper | doi.org/10.13182/NSE66-A18299
Heterogeneity Calculation for Fast Reactors by a Perturbation Method
F. Storrer, A. Khairallah, M. Cadilhac, P. Benoist
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 153-164
Technical Paper | doi.org/10.13182/NSE66-A18300
A Method for Predicting the Penetration and Slowing Down of Neutrons in Reactor Shields
L. Hjärne, M. Leimdörfer
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 165-174
Technical Paper | doi.org/10.13182/NSE66-A18301
Control of Reactivity in High Conversion Ratio, Plutonium-Fueled Thermal Power Reactors
G. Srikantiah
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 175-183
Technical Paper | doi.org/10.13182/NSE66-A18302
Reactor Noise Analysis by Photon Observation
R. J. Gelinas, R. K. Osborn
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 184-192
Technical Paper | doi.org/10.13182/NSE66-A18303
An Electron Shielding Analysis for Space Vehicles
B. W. Mar
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 193-199
Technical Paper | doi.org/10.13182/NSE66-A18304
A New Variant to the Exponential Transformation Technique in Monte Carlo Shielding Calculations
A. B. Chilton
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 200-208
Technical Paper | doi.org/10.13182/NSE66-A18305
Consistency in the Analysis of High-Buckling Critical Experiments
W. J. Eich, H. T. Williams, Jr.
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 209-211
Technical Note | doi.org/10.13182/NSE66-A18306
Neutron Diffusion Parameters in Benzene
V. C. Boffi, B. Marisco, V. G. Molinari, R. Scozzafava
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 211-212
Technical Note | doi.org/10.13182/NSE66-A18307
Neutron Thermalization and Diffusion in Nonisothermal Media
Bal Raj Sehgal
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 212-216
Technical Note | doi.org/10.13182/NSE66-A18308
On Thermal-Neutron Pulse Propagation
K. Y. Cheung, G. H. Miley
Nuclear Science and Engineering | Volume 24 | Number 2 | February 1966 | Pages 216-217
Technical Note | doi.org/10.13182/NSE66-A18309

Number 3

Table of Contents
Computer Code Abstract: WIGL2 (G. R. Dalton, Q. L. Miller)
Computer Code Abstract: DPN Roots (A. V. Vota)
Classical Scientific Papers — Physics (Don M. Yost)
Two-Group Reactor Theory (George I. Bell)
A New System of Chemical Philosophy (R. E. Meyer)

The Start-up Transient Behavior of Thermoelectric Generators with Temperature-Dependent Physical Parameters
David Tai-Ko Shaw
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE66-A17636
An Analysis of Continuous Reactor Refueling
Sigeru Yasukawa
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 239-245
Technical Paper | doi.org/10.13182/NSE66-A17637
The Space Dependence of Reactor Noise I-Theory
James R. Sheff, Robert W. Albrecht
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 246-259
Technical Paper | doi.org/10.13182/NSE66-A17638
Critical Calculations of the Slab Reactors
Krystyna Kowalska
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 260-271
Technical Paper | doi.org/10.13182/NSE66-A17639
The Calculation of Neutron Spectra in Reflected Cores and Reflector Regions
S. T. Perkins
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 284-290
Technical Paper | doi.org/10.13182/NSE66-A17640
A Numerical Study of the Method of Weighted Residuals
G. C. Pomraning
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 291-301
Technical Paper | doi.org/10.13182/NSE66-A17641
Monte Carlo Investigation of the Heterogeneity of Fast Reactor Cores
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 302-304
Technical Note | doi.org/10.13182/NSE66-A17642
On the Diffusion of Neutrons in a Reactor Lattice
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 304-306
Technical Note | doi.org/10.13182/NSE66-A17643
Properties of the P_L and Double-P_L Relaxation Lengths in the Presence of Anistropic Scattering
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 306-307
Technical Note | doi.org/10.13182/NSE66-A17644
Time-Dependent Green's Function
Nuclear Science and Engineering | Volume 24 | Number 3 | March 1966 | Pages 307-308
Technical Note | doi.org/10.13182/NSE66-A17645

Number 4

Table of Contents
Radiochemical Methods of Analysis (Paul L. Kirk)
Energetics in Metallurgical Phenomena—Volume 1 (S. Bradford McRickard)
Refractory Transition Metal Compounds; High-Temperature Cermets (E. F. Juenke)
Effects of Radiation on Semiconductors (J. H. Crawford, Jr.)
Note on the Use of Generalized Functions and the Poincaré-Bertrand Formula in Neutron Transport Theory (H. G. Kaper)
Comment to the Preceding Letter by Kaper (I. Kuscer, N. J. McCormick)
Further Comments on the Use of Generalized Functions in Neutron Transport Theory (A. M. Jacobs, R. D. Meyer)

Heat Transport by Radiation in Solids
F. Engelmann, H. E. Schmidt
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 317-321
Technical Paper | doi.org/10.13182/NSE66-A16399
Fission-Fragment Transport Effects as Related to Fission-Electric-Cell Efficiencies
George H. Miley
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 322-331
Technical Paper | doi.org/10.13182/NSE66-A16400
Melting Point Determination of Uranium Monophosphide
Y. Baskin
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 332-335
Technical Paper | doi.org/10.13182/NSE66-A16401
Spectrophotometry of Aqueous Homogeneous Reactor Fuel Solutions from 4 to 280°C and 0 to 930 psi(abs)
W. C. Waggener, A. J. Weinberger, R. W. Stoughton
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 336-343
Technical Paper | doi.org/10.13182/NSE66-A16402
A Method for Calculating the Flux Evolution in a Fast-Neutron Multiplying Medium as a Function of Time, Space, and Energy
F. Storrer, P. Govaerts, F. Ebersoldt, P. Hammer
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 344-348
Technical Paper | doi.org/10.13182/NSE66-A16403
Multigroup Calculations of the Fast Spectrum and Fast Fission Effect
J. Helholtz, W. Rothenstein
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 349-355
Technical Paper | doi.org/10.13182/NSE66-A16404
Effect of Delayed Neutrons on the Stability of a Nuclear Power Reactor
Wiktor Baran, Kenneth Meyer
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 356-361
Technical Paper | doi.org/10.13182/NSE66-A16405
Boundary Conditions in Gap Geometry
W. Rothenstein, J. Helholtz
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 362-374
Technical Paper | doi.org/10.13182/NSE66-A16406
A Rigorous Expression for Shape of a Doppler-Broadened Resonance
Yukio Ishiguro
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 375-380
Technical Paper | doi.org/10.13182/NSE66-A16407
Use of Discrete-Ordinates Methods for Solution of Photon Transport Problems
K. D. Lathrop
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 381-388
Technical Paper | doi.org/10.13182/NSE66-A16408
The Effect of Randomness on Group Cross Sections
Charles N. Kelber, Philip H. Kier
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 389-393
Technical Paper | doi.org/10.13182/NSE66-A16409
Scattering of Neutrons by Polyethylene
W. L. Whittemore
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 394-409
Technical Paper | doi.org/10.13182/NSE66-A16410
On the Maximum Absorption Theorem
Noel Corngold
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 410-412
Techincal Note | doi.org/10.13182/NSE66-A16411
Neutron Fluctuations in a Multiplying Medium
Masuhiko Otsuka, Keiichi Saito
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 412-414
Techincal Note | doi.org/10.13182/NSE66-A16412
Subcritical Determination of Relative Natural-Neutron-Source Strengths
R. H. Rohr, M. L. Storm
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 414-417
Techincal Note | doi.org/10.13182/NSE66-A16413
Variation of the Transport Mean Free Path in Graphite with Temperature
J. A. De Juren
Nuclear Science and Engineering | Volume 24 | Number 4 | April 1966 | Pages 417-418
Techincal Note | doi.org/10.13182/NSE66-A16414