Volume 32

Number 2

Table of Contents
FIGRO(L. L. Lynn)
2DB: A Two-Dimensional Fast-Reactor Burnup Code(W. W. Little, Jr., R. W. Hardie)
GLUB-1(L. L. Lynn)
Completeness in Science(Robert T. Lagemann)
The New Age in Physics(Roger W. Clapp, Jr.)
Sourcebook on Atomic Energy(William C. Pettus)
Servomechanisms(M. A. Schultz)
Radiation Heat Transfer(C. L. Tien)
Doppler Effect in Fissioning Plasma Reactors(H. F. Atwater)
Comments on Massel and Feix's Technical Note on Neutron Diffusion Using a Modulated Source(M. J. Ohanian)

Characteristics of a Tapered Cascade for Isotope Separation by Gaseous Diffusion

Kunio Higashi, Akio Oya, Jun Oishi

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 159-165

Technical Paper / dx.doi.org/10.13182/NSE68-A19728

Gamma Radiation Fluxes Near a Ground-Air Interface Using an Image Source Technique

C. Eisenhauer

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 166-177

Technical Paper / dx.doi.org/10.13182/NSE68-A19729

A Formalism for Calculation of Neutron Induced Gamma-Ray Production Cross Sections and Spectra

R. J. Howerton, E. F. Plechaty

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 178-183

Technical Paper / dx.doi.org/10.13182/NSE68-A19730

Calculation of the Penetration of Gamma Rays Through Slabs by the Method of Invariant Imbedding

A. Shimizu

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 184-194

Technical Paper / dx.doi.org/10.13182/NSE68-A19731

Some Neutron Reaction Cross Sections for ^{111, 112}Cd, ⁸⁷Sr, and ⁵⁸Ni

J. K. Temperley

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 195-200

Technical Paper / dx.doi.org/10.13182/NSE68-A19732

Study of Lattices of Graphite with Empty Channels by Means of the Pulsed Source Technique

V. Deniz, J. G. Le Ho, M. Sagot

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 201-224

Technical Paper / dx.doi.org/10.13182/NSE68-A19733

A New Method of Approximation of the Boltzmann Equation

Pierre Benoist, Alain Kavenoky

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 225-232

Technical Paper / dx.doi.org/10.13182/NSE68-A19734

Interface Conditions for Few-Group Neutron Diffusion Equations with Flux-Adjoint Weighted Constants

A. J. Buslik

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 233-240

Technical Paper / dx.doi.org/10.13182/NSE68-A19735

Formal Solution to the Neutron Moderation Problem in Nonhydrogenous Infinite Homogeneous Media

Leib Finkelstein

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 241-248

Technical Paper / dx.doi.org/10.13182/NSE68-A19736

The Study of One-Speed Multiregion Transport Problems in Plane Geometry by the Method of Boundary Sources

R. Beauwens, J. Devooght

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 249-261

Technical Paper / dx.doi.org/10.13182/NSE68-A19737

On the Use of ¹⁶⁴Dy, ¹⁷⁶Lu, and ²³⁹Pu in Thermal-Neutron Spectrum Determinations

J. J. Volpe

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 262-264

Technical Note / dx.doi.org/10.13182/NSE68-A19738

Effective Cadmium Cutoff Energies for Finite Cylindrical Filters with Finite-Size Detectors

S. S. Glickstein, W. J. Hall

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 264-265

Technical Note / dx.doi.org/10.13182/NSE68-A19739

Resonance Parameters for ²³⁶U from Integral Measurements

N. P. Baumann, J. D. Halford, D. J. Pellarin

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 265-267

Technical Note / dx.doi.org/10.13182/NSE68-A19740

A Technique for the Determination of Ratios of Effective Cross Sections from Reactor Fuel Burnup Data

R. P. Matsen

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 267-270

Technical Note / dx.doi.org/10.13182/NSE68-A19741

The C_n Method of Approximating the Boltzmann Equation in Cylindrical Geometry

Pierre Benoist, Alain Kavenoky

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 270-271

Technical Note / dx.doi.org/10.13182/NSE68-A19742

Approximate Zero-Power Describing Function Valid at All Frequencies

A. Ziya Akcasu, Louis M. Shotkin

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 271-273

Technical Note / dx.doi.org/10.13182/NSE68-A19743

On Controllability of Neutron-Flux Distribution

Nobuhide Suda

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 273-274

Technical Note / dx.doi.org/10.13182/NSE68-A19744