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Volume 23

Number 4

Table of Contents
Controlled Thermonuclear Reactions(Albert Simon)
Decay Constant of a Neutron Pulse Inside a Finite Solid Moderator Assembly(L. S. Kothari)
Decay Constant of a Neutron Pulse(Noel Corngold)
On the Use of the Poincaré-Bertrand Formula in Neutron Transport Theory(I. Kuščer, N. J. McCormick)
A Note on the Adjoint Function in the Time Optimal Xenon Shutdown Problem(Jeffery Lewins)

Evaluation of Thermocouple Thermal-Loading Errors for a Surface-Attached Thermocouple on a Flat-Plate Fuel Element

J. H. Brindley

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 313-328

Technical Paper / dx.doi.org/10.13182/NSE65-A21067

Axial Heat Conduction in Reactor Fuel Elements

J. F. Thorpe

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 329-334

Technical Paper / dx.doi.org/10.13182/NSE65-A21068

The Solubility of Helium in Uranium Dioxide

Firooz Rufeh, Donald R. Olander and Thomas H. Pigford

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 335-338

Technical Paper / dx.doi.org/10.13182/NSE65-A21069

An Attempt to Measure Directly the Slowing Down Age of (D,D) Neutrons in Paraffin

B. Grimeland and G. Seierstad

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 339-343

Technical Paper / dx.doi.org/10.13182/NSE65-A21070

Calculation of Differential Fast-Neutron Spectra from Threshold-Foil Activation Data by Least-Squares Series Expansion Methods

G. Di Cola and A. Rota

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 344-353

Technical Paper / dx.doi.org/10.13182/NSE65-A21071

Thermal-Neutron-Induced-Recoil Defects in Cadmium Sulfide

Robert B. Oswald, Jr., and Chihiro Kikuchi

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 354-360

Technical Paper / dx.doi.org/10.13182/NSE65-A21072

Study of a Slightly Enriched UO₂ Lattice with H:U=0.42 — Measurement and Analysis

W. Baer, J. Hardy, Jr., D. Klein, J. J. Volpe, B. L. Palowitch and F. S. Frantz, Jr.

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 361-367

Technical Paper / dx.doi.org/10.13182/NSE65-A21073

Resonance Capture and Doppler Coefficient in Cylindrical Uranium Fuel Elements

T. D. Beynon, I. S. Grant

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 368-379

Technical Paper / dx.doi.org/10.13182/NSE65-A21074

Polarization Effects on Neutron Transport

George I. Bell and Walter B. Goad

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 380-391

Technical Paper / dx.doi.org/10.13182/NSE65-A21075

Doppler Coefficient Measurements for ²³⁵U in Fast-Reactor Spectra

P. I. Amundson, J. M. Gasidlo

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 392-393

Technical Note / dx.doi.org/10.13182/NSE65-A21076

Thermal Disadvantage Factors in Very Undermoderated Water-Uranium Oxide Lattices

Allen R. Boynton

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 393-395

Technical Note / dx.doi.org/10.13182/NSE65-A21077

A Method for Computing

G. C. Pomraning

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 395-397

Technical Note / dx.doi.org/10.13182/NSE65-A21078

Equivalence of the Time Optimal and Minimax Solutions to the Xenon Shutdown Problem

John J. Roberts, Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 397-399

Technical Note / dx.doi.org/10.13182/NSE65-A21079