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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE76-A26910