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Volume 24

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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)
Nuclear Reactions Volume II(Herbert Goldstein)
The Sorby Centennial Symposium On The History Of Metallurgy(William A. Mugde)

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE66-A18309

Number 3

Table of Contents
Computer Code Abstract: DPN Roots(A. V. Vota)
Computer Code Abstract: WIGL2(G. R. Dalton, Q. L. Miller)
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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE66-A16414