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Volume 60

Number 4

Table of Contents
Comments on “Analysis of the Microfission Reactor Concept”(J. Ligou, W. Seifritz)
Response to “Comments on ‘Analysis of the Microfission Reactor Concept’”(Randall K. Cole, Jr.)
Comments on “Analysis of the Microfission Reactor Concept”(A. D. Krumbein)
Task-3(Suresh Garg, Feroz Ahmed)

Application of Walsh Functions to Neutron Transport Problems—I. Theory

Thomas J. Seed, Robert W. Albrecht

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 337-345

Technical Paper / dx.doi.org/10.13182/NSE76-A26895

Application of Walsh Functions to Neutron Transport Problems—II. Analysis

Thomas J. Seed, Robert W. Albrecht

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 346-356

Technical Paper / dx.doi.org/10.13182/NSE76-A26896

Neutron Transport and Diffusion in Inhomogeneous Media. II

Edward W. Larsen

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 357-368

Technical Paper / dx.doi.org/10.13182/NSE76-A26897

Measurement of the Uranium-235 Fission Cross Section over the Neutron Energy Range 1 to 6 MeV

D. M. Barton, B. C. Diven, G. E. Hansen, G. A. Jarvis, P. G. Koontz, R. K. Smith

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 369-382

Technical Paper / dx.doi.org/10.13182/NSE76-A26898

A Measurement of the Fission Cross Section of Uranium-235 from 100 eV to 680 keV

J. B. Czirr, G. S. Sidhu

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 383-389

Technical Paper / dx.doi.org/10.13182/NSE76-A26899

Measurement of Neutron Radiative Capture in Cobalt-59

R. R. Spencer, H. Beer

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 390-398

Technical Paper / dx.doi.org/10.13182/NSE76-A26900

Neutron Resonance Spectroscopy in Natural Copper

M. S. Pandey, J. B. Garg

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 399-404

Technical Paper / dx.doi.org/10.13182/NSE76-A26901

Measured and Calculated Neutron Albedo for Concrete and Iron

Walter Meyer, J. W. Leighty, J. W. Thiesing, D. H. Timmons

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 405-420

Technical Paper / dx.doi.org/10.13182/NSE76-A26902

Design of Ideal Cascades of Gas Centrifuges with Variable Separation Factors

D. R. Olander

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 421-434

Technical Paper / dx.doi.org/10.13182/NSE76-A26903

Molten Clad Motion Model for Fast Reactor Loss-of-Flow Accidents

M. Ishii, W. L. Chen, M. A. Grolmes

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 435-451

Technical Paper / dx.doi.org/10.13182/NSE76-3

Simple Heat Conduction Model with Phase Change for Reactor Fuel Pin

W. L. Chen, M. Ishii, M. A. Grolmes

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 452-460

Technical Paper / dx.doi.org/10.13182/NSE76-A26905

The Monte Carlo Nonuniform Sampling Technique Applied to the Klein-Nishina Probability Density Function

Y. S. Horowitz, A. Dubi, S. Mordechai

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 461-463

Technical Note / dx.doi.org/10.13182/NSE76-A26906

The Determination of Homogenized Group Diffusion Theory Parameters

John G. Kollas and Allan F. Henry

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 464-471

Technical Note / dx.doi.org/10.13182/NSE76-A26907

Neutron Thermalization in Light Water—Measurement and Calculation of Spectra

M. J. Abbate, J. V. Lolich, T. F. Parkinson

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 471-477

Technical Note / dx.doi.org/10.13182/NSE76-A26908

Cross-Section Measurements for Charged Particle Fusion Reactors: The ⁶Li(³He, p) 2α Reaction

C. R. Gould, J. R. Boyce

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 477-481

Technical Note / dx.doi.org/10.13182/NSE76-A26909

An Estimate of the Yield of Photoneutrons from Beryllium Using a LINAC as the X-Ray Source

G. S. Khandelwal, W. M. Pritchard, J. J. Singh

Nuclear Science and Engineering / Volume 60 / Number 4 / August 1976 / Pages 481-482

Technical Note / dx.doi.org/10.13182/NSE76-A26910