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Number 1

Table of Contents
Comment on the Drift-Flux Approximation in Transient Two-Phase Flows (Robert W. Lyczkowski)
Comments on Neutron-Induced Fission in a Compressed DT-Pu Plasma (W. Seifritz)
Reply to “Comment on the Drift-Flux Approximation in Transient Two-Phase Flows” (J. R. Travis, W. C. Rivard, F. H. Harlow)
Thermal Analysis of Liquid-Metal Fast Breeder Reactors (G. McAreavey, J. B. Love)
Energy Conversion Engineering (M. S McCay)

Core Control Optimization for Scheduled Load Changes in Large Pressurized Water Reactors
Jorma Karppinen, Rob M. Versluis, Bjørn Blomsnes
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE79-A20325
Neutron Yields from Alpha-Particle Bombardment
J. K. Bair, J. Gomez del Campo
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 18-28
Technical Paper | doi.org/10.13182/NSE71-18
Calculation of the Total Flux at a Point by the Monte Carlo Track Rotation Estimator
A. Dubi, Y. S. Horowitz, H. Rief
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 29-45
Technical Paper | doi.org/10.13182/NSE79-A20327
A Finite Moments Algorithm for Particle Transport Problems
R. Vaidyanathan
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 46-54
Technical Paper | doi.org/10.13182/NSE79-A20328
Clusius-Dickel Effect in a Nuclear Fuel Rod
S. K. Loyalka, V. K. Chandola
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 55-57
Technical Note | doi.org/10.13182/NSE79-A20329
The Particle Spectrum to Be Expected from a D-T Plasma
H. Liskien
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 57-59
Technical Note | doi.org/10.13182/NSE79-A20330
A Correlation Technique for Resonance Calculations
M. V. Gregory
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 59-64
Technical Note | doi.org/10.13182/NSE79-A20331
On the Validity of the Extended Transport Cross-Section Correction for Low-Energy Electron Transport
J. E. Morel
Nuclear Science and Engineering | Volume 71 | Number 1 | July 1979 | Pages 64-71
Technical Note | doi.org/10.13182/NSE79-A20332

Number 2

Table of Contents
On the Eigenvalues of the Stationary and Time-Dependent Boltzmann Equation in Its Integro-Differential and Integral Forms (V. Protopopescu)
Comments on “On the Eigenvalues of the Stationary and Time-Dependent Boltzmann Equation in Its Integro-Differential and Integral Forms” (N. G. Sjöstrand)
Nuclear Reactor Theory and Design (N. C. Francis)

Factorized Kernels and the DKPL Solution to the Third Form of the Neutron Transport Equation in a Rectangular Parallelepiped
A. Bassini, F. Premuda, W. A. Wassef
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 87-99
Technical Paper | doi.org/10.13182/NSE79-A20401
Discrete Transfer Cross-Section Expansion for Time-Dependent Neutron Transport
F. Beranek, R. W. Conn
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 100-110
Technical Paper | doi.org/10.13182/NSE79-A20402
Computational Efficiency of Numerical Methods for the Multigroup, Discrete-Ordinates Neutron Transport Equations: The Slab Geometry Case
R. E. Alcouffe, E. W. Larsen, W. F. Miller, Jr., B. R. Wienke
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 111-127
Technical Paper | doi.org/10.13182/NSE71-111
Analysis of Error in Monte Carlo Transport Calculations
Thomas E. Booth, Edmond D. Cashwell
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 128-142
Technical Paper | doi.org/10.13182/NSE79-A20404
Reactivity Measurements in a Thorium Critical Assembly
Keiji Kobayashi, Junnosuke Horie, Keiji Kanda, Toshikazu Shibata
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 143-153
Technical Paper | doi.org/10.13182/NSE79-A20405
Critical Experiments with Lattices of 475-wt%-²³⁵U-Enriched UO₂ Rods in Water
J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 154-163
Technical Paper | doi.org/10.13182/NSE79-4
Effect of Soluble Neutron Absorbers on the Criticality of Low-Uranium-235 Enriched UO₂ Lattices
R. C. Lloyd, B. M. Durst, E. D. Clayton
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 164-169
Technical Paper | doi.org/10.13182/NSE79-A20407
Characteristics of a Beam-Driven Deuterium-Fueled Fusion-Fission Reactor System
K. F. Schoepf, A. A. Harms
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 170-181
Technical Paper | doi.org/10.13182/NSE79-A20408
^{104,105,106,108,110}Pd (n,γ) Cross Sections Above 2.6 keV
R. L. Macklin, J. Halperin, R. R. Winters
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 182-191
Technical Paper | doi.org/10.13182/NSE79-A20409
Multiple-Jet Thermal Mixing in a Piping Tee
Paul S. Lykoudis, Robert C. Hagar
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 192-201
Technical Paper | doi.org/10.13182/NSE79-A20410
Accuracy and Computational Time of a Hierarchy of Growth Rate Definitions for Breeder Reactor Fuel
P. J. Maudlin, R. C. Borg, K. O. Ott
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 202-205
Technical Note | doi.org/10.13182/NSE79-A20411
⁶Li(n,α)T Cross Section from 70 to 3000 keV from the ²³⁵U(n,f) Calibration of a Thin Glass Scintillator
R. L. Macklin, R. W. Ingle, J. Halperin
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 205-208
Technical Note | doi.org/10.13182/NSE79-A20412
The Energy Dependence of Fission Fragment Anisotropy in Fast-Neutron-Induced Fission of Uranium-235
S. Ahmad, M. M. Islam, A. H. Khan, M. Khaliquzzaman, M. Husain, M. A. Rahman
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 208-211
Technical Note | doi.org/10.13182/NSE79-A20413
The Calculation of the Void Fraction by Slip Ratio Correlations: A General Method
F. Norelli
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 212-215
Technical Note | doi.org/10.13182/NSE79-A20414
Thermal Radiation Properties of Interfaces Between Nuclear Reactor Materials
S. H. Chan, H. H. Tseng
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 215-227
Technical Note | doi.org/10.13182/NSE79-A20415

Number 3

Table of Contents
On the Quasi-Static Synthesis Method for Space-Time Dynamics Problems (J. B. Doshi)
Reply to “On the Quasi-Static Synthesis Method for Space-Time Dynamics Problems” (Bruce I. Hauss, William E. Kastenberg)
MHD Instabilities (George H. Miley)

The Dispersion and Spheroidization Treatment of δ Zirconium Hydride and Its Effect on Corrosion Resistance
Shi-Chien Lin, Michiko Hamasaki, Yii-Der Chuang
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 237-250
Technical Paper | doi.org/10.13182/NSE79-A19061
The Effect of Dispersion and Spheroidization Treatment of δ Zirconium Hydrides on the Mechanical Properties of Zircaloy
Shi-Chien Lin, Michiko Hamasaki, Yii-Der Chuang
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 251-266
Technical Paper | doi.org/10.13182/NSE79-A19062
Statistical Evaluation of Major Human Errors During the Development of New Technological Systems
G. Campbell, K. O. Ott
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 267-279
Technical Paper | doi.org/10.13182/NSE79-A19063
Cross Sections for ⁶Li(⁶Li,⁵He)⁷Be, ⁶Li(d,n)⁷Be, and ¹⁹F(⁶Li,p)²⁴Na
Lawrence Ruby, Robert V. Pyle, Yue-Chau Wong
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 280-286
Technical Paper | doi.org/10.13182/NSE79-A19064
Thor, A Thorium-Reflected Plutonium-Metal Critical Assembly
G. E. Hansen, H. C. Paxton
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 287-293
Technical Paper | doi.org/10.13182/NSE79-A19065
Penetration of Secondary Neutrons and Photons from a Graphite Assembly Exposed to 52-MeV Protons
Kazuo Shin, Yoshitomo Uwamino, Mitsuo Yoshida, Tomonori Hyodo, Takashi Nakamura
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 294-300
Technical Paper | doi.org/10.13182/NSE79-A19066
The Energy Distribution of Antineutrinos Originating from the Decay of Fission Products in a Nuclear Reactor
G. Rudstam, K. Aleklett
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 301-308
Technical Paper | doi.org/10.13182/NSE79-A19067
Reactor Dynamic Perturbation Measurement
R. Fuge, D. Ziegenbein
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 309-318
Technical Paper | doi.org/10.13182/NSE79-A19068
An Interpretation of the Quadratic Approximation in Zero Power Reactor Noise Analysis
F. Carloni, M. Marseguerra
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 319-326
Technical Paper | doi.org/10.13182/NSE79-A19069
Comparison of Calculations and Measurements of Fission Product Decay Heat for Uranium-235 and Plutonium-239 for Cooling Times >5 × 10⁴ s
K. Shure, O. J. Wallace, J. C. Connor
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 327-330
Technical Note | doi.org/10.13182/NSE79-A19070
An Improvement of the PALLAS Discrete-Ordinates Transport Code
Nobuo Sasamoto, Kiyoshi Takeuchi
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 330-342
Technical Note | doi.org/10.13182/NSE79-A19071