Home / Publications / Journals / Nuclear Science and Engineering / Volume 24 / Number 2

Volume 24

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