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Volume 60

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Number 1

Table of Contents
Advances in Nuclear Science and Technology, Vol. 7(E. Richard Cohen)

Transient Freezing of Liquids in Tube Flow

F. B. Cheung, L. Baker, Jr.

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE76-A26851

An Analysis of Transients in Experiments on Loss-of-Coolant Accidents

Makoto Sobajima

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 10-18

Technical Paper / dx.doi.org/10.13182/NSE76-A26852

Present Status of Photofission of Actinides Near Threshold

B. S. Bhandari, I. C. Nascimento

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 19-26

Technical Paper / dx.doi.org/10.13182/NSE76-A26853

Measurements of the Neutron Spectra from Materials Used in Fusion Reactors and Calculations Using the ENDF/B-III and -IV Neutron Libraries

L. F. Hansen, C. Wong, T. Komoto, J. D. Anderson

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 27-35

Technical Paper / dx.doi.org/10.13182/NSE76-A26854

Production of Low-Energy Gamma Rays by Neutron Interactions with Fluorine for Incident Neutron Energies Between 0.1 and 20 MeV

G. L. Morgan, J. K. Dickens

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 36-43

Technical Paper / dx.doi.org/10.13182/NSE76-A26855

Measurement and Normalization of the Relative Plutonium-241 Fission Cross Section in the Thermal and Low-Resonance Energy Region

C. Wagemans, A. J. Deruytter

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 44-52

Technical Paper / dx.doi.org/10.13182/NSE76-A26856

Neutron-Capture Cross Sections of the Europium and Lutetium Isotopes from 0.01 to 10 eV

J. F. Widder

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 53-61

Technical Paper / dx.doi.org/10.13182/NSE76-A26857

Fast-Pulse Reactor Operation with Reflector Control and a 106-mm-diam Glory Hole

A. H. Kazi

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 62-73

Technical Paper / dx.doi.org/10.13182/NSE76-A26858

Finite Difference Equations for Transport Equation in Toroidal Geometry

Jungchung Jung

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 74-86

Technical Paper / dx.doi.org/10.13182/NSE76-A26859

Dispersion of Radioactive Materials by a Fluid Flowing in a Pipe

S. A. Kushneriuk, J. M. Blair

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 87-95

Technical Note / dx.doi.org/10.13182/NSE76-A26860

Charge Released by Beta-Decaying Self-Powered Neutron Detectors

H. D. Warren, N. L. Snidow

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 95-97

Technical Note / dx.doi.org/10.13182/NSE76-A26861

A Comparison of Some Eigenvalues in Reactor Theory

Y. Ronen, D. Shvarts, J. J. Wagschal

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 97-101

Technical Note / dx.doi.org/10.13182/NSE76-A26862

Equivalence of Transformed and Invariant Radiative Transfer Kernels

B. R. Wienke

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 101-103

Technical Note / dx.doi.org/10.13182/NSE76-A26863

Time-Dependent Moments of the Monoenergetic Transport Equation in Spherical and Cylindrical Geometry

B. D. Ganapol

Nuclear Science and Engineering / Volume 60 / Number 1 / May 1976 / Pages 103-105

Technical Note / dx.doi.org/10.13182/NSE76-A26864

Number 2

Table of Contents
Melt-III(A. E. Waltar, W. L. Partain, D. C. Kolesar, L. D. O'Dell, A. Padilla, Jr., J. C. Sonnichsen, N. P. Wilburn, H. J. Willenberg)

Numerical Solution of the Transport Equation by Collocation with Bivariate Splines

L. Finkelstein, A. Krumbein

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 113-119

Technical Paper / dx.doi.org/10.13182/NSE76-A26867

Finite Element Solutions of Space-Time Nonlinear Reactor Dynamics

Dong H. Nguyen, David Salinas

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE76-A26868

Prediction of Statistical Error in Monte Carlo Transport Calculations

Harvey J. Amster, M. Jahed Djomehri

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 131-142

Technical Paper / dx.doi.org/10.13182/NSE76-A26869

Criticality of Plutonium-Uranium Nitrate Solutions

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 143-146

Technical Paper / dx.doi.org/10.13182/NSE76-A26870

A Pulsed Activation Measurement of the Doppler Effect of Uranium-238 over the Temperature Range 300 to 3115 K

S. K. Bhattacharyya, G. J. Russell, W. K. Foell

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 147-168

Technical Paper / dx.doi.org/10.13182/NSE76-A26871

Experimental and Theoretical Investigations of Tritium Production in a Controlled Thermonuclear Reactor Blanket Model

R. Herzing, L. Kuypers, P. Cloth, D. Filges, R. Hecker, N. Kirch

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 169-175

Technical Paper / dx.doi.org/10.13182/NSE76-A26872

Sodium-Water-Reaction Test and Evaluation for a Protected Bayonet-Tube Steam Generator

S. M. Cho, E. C. Govignon, G. J. Degutis

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 176-186

Technical Paper / dx.doi.org/10.13182/NSE76-A26873

Measurement of Cross Sections for the ⁵⁹Co(n,p)⁵⁹Fe Reaction Near Threshold

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 187-188

Technical Note / dx.doi.org/10.13182/NSE76-A26874

On-Line Prediction of the Power Distribution Within Boiling Water Reactors

Yasuo Nishizawa, Takashi Kiguchi, Hiroshi Motoda

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 189-192

Technical Note / dx.doi.org/10.13182/NSE76-A26875

Number 3

Table of Contents
Advances in Nuclear Science and Technology, Vol. 8(Lothar W. Nordheim)

Exact Doppler Broadening of Tabulated Cross Sections

Dermott E. Cullen, Charles R. Weisbin

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 199-229

Technical Paper / dx.doi.org/10.13182/NSE76-1

Total Neutron Cross Section of Lead

Keiji Kanda, Otohiko Aizawa

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 230-234

Technical Paper / dx.doi.org/10.13182/NSE76-A26879

14.6-MeV Neutron Activation Cross Section for the Xenon Isotopes

R. A. Sigg and P. K. Kuroda

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 235-238

Technical Paper / dx.doi.org/10.13182/NSE76-A26880

Monte Carlo Analysis of Direct Measurements of the Fission Neutron Yield Per Absorption by Uranium-233 and Uranium-235 of Monochromatic Neutrons

J. J. Ullo and M. Goldsmith

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 239-250

Technical Paper / dx.doi.org/10.13182/NSE76-A26881

Monte Carlo Analysis of Thermal-Spectrum Averaged Measurements of η of Uranium-233 and Uranium-235

M. Goldsmith and J. J. Ullo

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 251-261

Technical Paper / dx.doi.org/10.13182/NSE76-A26882

The Effective Delayed Neutron Fraction from Fission in an Unreflected Uranium Sphere from Time Correlation Measurements with Californium-252

J. T. Mihalczo

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 262-275

Technical Paper / dx.doi.org/10.13182/NSE76-4

Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies

Suresh Garg, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 276-287

Technical Paper / dx.doi.org/10.13182/NSE76-A26884

Space-Dependent Continuous Neutron Slowing Down Theory Utilizing Integral Transport Concepts

Gilbert Epstein, James Biffer, Martin Becker

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 288-301

Technical Paper / dx.doi.org/10.13182/NSE76-A26885

Transport Equations in Axisymmetric Toroidal Coordinates

Samuel L. Gralnick

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 302-310

Technical Paper / dx.doi.org/10.13182/NSE76-A26886

A Theory of Heat Transfer Between Two Gases in a Mixture

Kalimullah

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 311-314

Technical Note / dx.doi.org/10.13182/NSE76-A26887

The Release of Iodine from Iodide Salts by Gamma Radiolysis

Daniel Cubicciotti, John H. Davies

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 314-319

Technical Note / dx.doi.org/10.13182/NSE76-A26888

Fast-Neutron Excitation of Isomeric States in Indium

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 319-322

Technical Note / dx.doi.org/10.13182/NSE76-2

On the Average Energies of β⁻ Particles Emitted by Fission Products

M. Goldsmith, K. Shure

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 322-324

Technical Note / dx.doi.org/10.13182/NSE76-A26890

Collision Method in Spherical Geometry by Escape Probabilities

G. Bitelli, A. Turrin

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 324-326

Technical Note / dx.doi.org/10.13182/NSE76-A26891

The Importance of the Uranium-238 Inelastic Transfer Matrix for Fast-Reactor Analysis

T. Choong and E. Kujawski

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 326-329

Technical Note / dx.doi.org/10.13182/NSE76-A26892

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