Volume 49

Number 4

Table of Contents
TASK: A Generalized One-Dimensional Transport and Diffusion Kinetics Code(A. R. Buhl, H. L. Dodds, Jr., J. C. Robinson, R. A. Lillie)
Comments on Temperature-Dependent Intermediate Neutron Resonance Integrals(Yukio Ishiguro)
Reply to “Comments on Temperature-Dependent Intermediate Neutron Resonance Integrals”(Rubin Goldstein)
Reactivity Coefficients in Large Fast Power Reactors(F. Storrer)
Analyses of Temperature and Power Noise in Operating Nuclear Reactors(Keiichi Saito)
Subject Index
The Yield Stress Radiation Damage Function of Iron(G. R. Odette, T. O. Ziebold)

Radiation Transport in a Halfspace with a Source External to the Medium

G. C. Pomraning

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 409-417

Technical Paper / dx.doi.org/10.13182/NSE72-A22561

Time-Dependent Leakage Neutron Spectrum Studies of Some Small Hydrogenous Moderators

Kingsley F Graham, John M. Carpenter

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 418-437

Technical Paper / dx.doi.org/10.13182/NSE72-A22562

An Investigation of Non-Exponential Decay of Neutron Distributions in Graphite

Harold F. McFarlane

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 438-449

Technical Paper / dx.doi.org/10.13182/NSE72-A22563

The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations

Leo B. Levitt

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 450-457

Technical Paper / dx.doi.org/10.13182/NSE72-3

A New Method for Analysis of Pulsed Fast Neutron Experiments

Shin-ichi Ito

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 458-467

Technical Paper / dx.doi.org/10.13182/NSE72-A22565

Reactivity Worths of Boron, Tantalum, and Europium in a Fast Reactor Spectrum

R. J. Tuttle, T. H. Springer

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 468-481

Technical Paper / dx.doi.org/10.13182/NSE72-A22566

Reactor Depletion Analyzed as a Space-Time Problem

William J. Westlake, Jr., A. F. Henry

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 482-488

Technical Paper / dx.doi.org/10.13182/NSE72-A22567

Criticality of Graphite- and Polyethylene-Reflected Uranium (93.2%)-Metal Cylinders and Annuli

J. T. Mihalczo

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 489-504

Technical Paper / dx.doi.org/10.13182/NSE72-A22568

A Fitting Function for Energy Dissipation Curves of Fast Electrons

Tatsuo Tabata, Rinsuke Ito, Shigeru Okabe

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 505-506

Technical Notes / dx.doi.org/10.13182/NSE72-A22569

Temperature Dependence of Uranium Carbide Fission-Gas Swelling: An Analytical Evaluation

Alan J. Markworth

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 506-507

Technical Notes / dx.doi.org/10.13182/NSE72-A22570

Exact Collision Probabilities for Spherical Shells in a Homogeneous Medium

Tomas Lefvert

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 507-509

Technical Notes / dx.doi.org/10.13182/NSE72-A22571

The Transverse Diffusion Coefficient in a Square Lattice

T. Auerbach, W. Hälg, J. Mennig

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 509-515

Technical Notes / dx.doi.org/10.13182/NSE72-A22572

Optimization of Control Rod Programming and Loading Pattern in Multiregion Nuclear Reactor by the Method of Approximation Programming

Hiroshi Motoda

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 515-524

Technical Notes / dx.doi.org/10.13182/NSE72-A22573