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Report on Methods of Preparation of Inorganic Fluorides
From abstract: "Frequently it has been desirable to prepare pure anhydrous metal fluorides. Several general methods have proved satisfactory depending on the type of fluoride to be prepared."
Date:
November 11, 1943
Creator:
Priest, H. F.
System:
The UNT Digital Library
Factors Affecting the Chlorination of Uranium Compounds with Liquid Carbon Tetrachloride
Abstract: "A summary of the contents of numerous reports on the liquid phase proportion of uranium chloride."
Date:
November 11, 1946
Creator:
Lowrie, Robert Sydney & Larson, C. E.
System:
The UNT Digital Library
Report on Zirconium Nitride
Report presenting the properties and method of preparation of zirconium nitride, a compound that was being considered for use in high temperatures due to its high melting point and hardness.
Date:
November 11, 1947
Creator:
Hall, George D.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: September 1960
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
November 11, 1960
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Safe Handling of Chlorine Trifluoride and the Chemistry of the Chlorine Oxides and Oxyfluorides
Abstract: A discussion of the potential hazards of chlorine trifluoride is presented and a series of safe handling procedures is recommended.
Date:
November 11, 1960
Creator:
Farrar, R. Lynn, Jr.
System:
The UNT Digital Library
Advanced Designs and Special Applications for Fast Breeders
The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy circulated and cooled by a jet of sodium, (5) settled-bed core, (6) molten salt concept, and (7) paste-fuel system.
Date:
November 11, 1963
Creator:
Hammond, R. Philip
System:
The UNT Digital Library
Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors
Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.
Date:
November 11, 1963
Creator:
Cohen, K. P.; Greebler, P.; McNelly, M. J.; Murphy, P. M.; Sherer, D. B. & Zebroski, E. L.
System:
The UNT Digital Library
Statistical Techniques Used in the Specific Zirconium Alloy Design Program
Technical report describing the statistically designed empirical approach being used to choose a candidate Zr alloy optimum with respect to corrosion and hydriding rates in steam and having acceptable mechanical properties. The statistical techniques used and the reasons for their use are discussed in detail, with emphasis on the estimation of corrosion rates. Estimation of response surfaces is also considered.
Date:
November 11, 1963
Creator:
Jaech, John L.
System:
The UNT Digital Library