Home / Publications / Journals / Nuclear Science and Engineering / Volume 26 / Number 4

Volume 26

Number 4

Table of Contents
Iterative Solution of Elliptic Systems and Application to the Neutron Diffusion Equations of Reactor Physics(Harold Greenspan)
The Safe Transport of Radioactive Materials(H. C. Paxton)
Exact Solution of the Problem of Goldstein and Cohen(T. S. Horner and A. Keane)

An Experimental Study of the Time Dependence of the Beta Energy Spectrum from ²³⁵U Fission Fragments

J. W. Kutcher, M. E. Wyman

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 435-446

Technical Paper / dx.doi.org/10.13182/NSE66-A18414

Asymptotic and Transient Spectra in Incoherent Media

S. K. Trikha, P. S. Grover

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 447-452

Technical Paper / dx.doi.org/10.13182/NSE66-A18415

Thermal-Neutron Flux Perturbation by Dysprosium-Aluminum Foils in Water and Uranyl Fluoride-Water Solutions

Donald F. Shook, Donald Bogart, Donald L. Alger-and Robert A. Muller

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 453-461

Technical Paper / dx.doi.org/10.13182/NSE66-A18416

Spatial Variation of the Fast Neutron Flux in Cells of Slightly ²³⁵U-Enriched-Uranium Water-Moderated Lattices

J. Hardy, Jr., D. Klein, and R. Dannels

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 462-471

Technical Paper / dx.doi.org/10.13182/NSE66-A18417

Time-Dependent Neutron Flux in Pulsed Multiplying Assemblies

F. D. Judge and P. B. Daitch

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 472-486

Technical Paper / dx.doi.org/10.13182/NSE66-A18418

The Neutron Capture Cross Section of the Tungsten Isotopes from 0.01 to 10 Electron Volts

S. J. Friesenhahn, E. Haddad, F. H. Fröhner, and W. M. Lopez

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 487-499

Technical Paper / dx.doi.org/10.13182/NSE66-A18419

Fast Neutron Scattering from Beryllium, Sodium, and Aluminum

J. P. Chien and A. B. Smith

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 500-510

Technical Paper / dx.doi.org/10.13182/NSE66-A18420

Detector Effects on the Statistics of Neutron Fluctuations

R. K. Osborn and J. M. Nieto

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 511-516

Technical Paper / dx.doi.org/10.13182/NSE66-A18421

Analytical Continuation for Calculating Multigroup-Multizone Eigenvalue Problems using Lie Series

Ferdinand Cap and Alois Schett

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 517-521

Technical Paper / dx.doi.org/10.13182/NSE66-A18422

Reciprocity in Time-Dependent Neutron Transport Theory

I. Kuščer and N. J. McCormick

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 522-529

Technical Paper / dx.doi.org/10.13182/NSE66-A18423

Iterative Solution of the Neutron Slowing Down Equation

M. W. Dyos and A. Keane

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 530-533

Technical Paper / dx.doi.org/10.13182/NSE66-A18424

Particle Transport and Heat Transfer in Gas-Solid Suspension Flow Under the Influence of an Electric Field

Kun Min and B. T. Chao

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 534-546

Technical Paper / dx.doi.org/10.13182/NSE66-A18425

Reactor Organic Coolants: I. Characteristics of Irradiated Hydrogenated Terphenyls

M. Tomlinson, J. L. Smee, E. B. Winters, and M. C. Arneson

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 547-558

Technical Paper / dx.doi.org/10.13182/NSE66-A18426

Explicit Forms for Scattering Transformation Matrices

D. R. Harris

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 559-562

Technical Note / dx.doi.org/10.13182/NSE66-A18427

Quasistatic Treatment of Spatial Phenomena in Reactor Dynamics

Karl Ott

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 563-565

Technical Note / dx.doi.org/10.13182/NSE66-A18428

Appendix to the Preceeding

John T. Madell

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 564-565

Technical Note / dx.doi.org/10.13182/NSE66-A18429

The Polya Model and the Distribution of Neutrons in a Steady-State Reactor

Nicola Pacilio

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 565-569

Technical Note / dx.doi.org/10.13182/NSE66-A18430

Reality of Relaxation Lengths in Various Approximate Forms of the Slab Transport Equation

E. M. Gelbard and S. Kaplan

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 569-571

Technical Note / dx.doi.org/10.13182/NSE66-A18431

Fast-Neutron Spectra in Water and Graphite

L. Harris, Jr., G. Sherwood, and J. S. King

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 571-573

Technical Note / dx.doi.org/10.13182/NSE66-A18432

Measurements of Effective (Self-shielded) Neutron Cross Sections by a Fast Pulsed Method

E. Arai, H. Miessner, and K. H. Beckurts

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 573-575

Technical Note / dx.doi.org/10.13182/NSE66-A18433

Production of ^185mW in a Nuclear Reactor

Henry H. Kramer and Werner H. Wahl

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 575-577

Technical Note / dx.doi.org/10.13182/NSE66-A18434