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Volume 14

Number 2

Table of Contents
Crystallographic Data for the Hexagonal Crystal System(R. E. Frounfelker, M. A. Seitz, W. M. Hirthe)
On the Possibility of Using Model Experiments to Study Shielding Problems(Sven A. E. Johansson)
Two Regimes of Burnout (DNB) Correlated with Steam Energy Flow for Uniformly-Heated Channels(William J. Levedahl)
Minimum Mass Thin Fins with Internal Heat Generation(J. Ernest Wilkins, Jr.)
Xenon Spatial Oscillations(D. Randall, D. S. St. John)
The Transfer Cross Section Between Overlapping Thermal Groups(R. M. Pearce)
A Comment on the Treatment of Asymmetric Thin Regions(G. P. Calame)
Apparent Boiling of Uranium Oxide in the Center of a Fuel Pin During Transient Power Generation(J. H. Field, F. J. Leitz, M. J. McNelly, R. C. Nelson)
Plasticity and Creep of Metals(Robert E. Reed-Hill)
Atomic Energy Waste, Its Nature, Use and Disposal(Conrad P. Straub)
Reactor Handbook, Volume II, Fuel Reprocessing(Robert G. Hart)
Fuel Element Fabrication with Special Emphasis on Cladding Materials, Vols. 1 and 2(Donald C. Carmichael)
Stress Concentrations Around Holes(J. F. Patterson)
MURGATROYD(C. W. Nestor, Jr.)

The Development of High Purity Tantalum and Alloys for Liquid Plutonium Containment in LAMPRE I

Richard M. Bidwell, William E. Ferguson, Calvin C. Burwell, R. Philip Hammond, Keith V. Davidson, Walter R. Wykoff, Robert W. Anderson

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 109-122

Technical Paper / dx.doi.org/10.13182/NSE62-A28110

Corrosion Testing and Fuel Selection for LAMPRE I

C. C. Burwell, R. M. Bidwell, R. P. Hammond, J. E. Kemme, and B. J. Thamer

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 123-134

Technical Paper / dx.doi.org/10.13182/NSE62-A28111

Fabrication of Tantalum Fuel Containers for the LAMPRE I Molten Plutonium Reactor

G. S. Hanks, R. S. Kirby, J. M. Taub

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 135-143

Technical Paper / dx.doi.org/10.13182/NSE62-A28112

Fit of Yankee Startup Experiment Data to a Simple Reactor Analysis Model

Wm. Howard Arnold, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 144-152

Technical Paper / dx.doi.org/10.13182/NSE62-A28113

The Measurement of Dynamic Nuclear Reactor Parameters Using the Variance of the Number of Neutrons Detected

Robert W. Albrecht

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 153-158

Technical Paper / dx.doi.org/10.13182/NSE62-A28114

Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate-Hydrocarbon Diluent Solutions: I. Distribution Studies with TBP in Amsco 125-82 at Intermediate and Low Acidities

Wallace Davis, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 159-168

Technical Paper / dx.doi.org/10.13182/NSE62-A28115

Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate-Hydrocarbon Diluent Solutions: II. Densities, Molar Volumes, and Water Solubilities of TBP-Amsco 125-82-HNO₃-H₂O Solutions

Wallace Davis, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 169-173

Technical Paper / dx.doi.org/10.13182/NSE62-A28116

Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate—Hydrocarbon Diluent Solutions: III. Comparison of Literature Data

Wallace Davis, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 174-178

Technical Paper / dx.doi.org/10.13182/NSE62-A28117

Determination of Diffusion Coefficients for Thermal Neutrons in D₂O at 20, 100, 165, and 220°C

Norman P. Baumann

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 179-185

Technical Paper / dx.doi.org/10.13182/NSE62-A28118

Radiation of an Extended Source

M. J. Barrett

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 186-191

Technical Paper / dx.doi.org/10.13182/NSE62-A28119

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