32 results on '"Ferris L"'
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2. EXPERIMENTAL SURVEY OF CLOSE-COUPLED PROCESSING METHODS FOR FUELS CONTAINING URANIUM AND THORIUM
3. DECLADDING OF PWR BLANKET FUEL ELEMENTS WITH AQUEOUS AMMONIUM FLUORIDE SOLUTIONS
4. SAFETY, HEALTH PHYSICS, AND OPERATING PROCEDURES FOR CHEMICAL TECHNOLOGY DIVISION BERYLLIUM FACILITY
5. ESTIMATED BEHAVIOR OF TITANIUM IN MSBR CHEMICAL PROCESSING SYSTEMS.
6. LIQUID--VAPOR EQUILIBRIA IN LiF--BeF$sub 2$ AND LiF--BeF$sub 2$--ThF$sub 4$ SYSTEMS.
7. CHEMICAL TECHNOLOGY DIVISION ZIRFLEX PROCESS FOR PWR BLANKET FUEL. II. REVISED FLOWSHEET
8. BALL-MILLING OF GRAPHITE-BASE REACTOR FUEL
9. RATES OF GAS EVOLUTION FROM THE REACTIONS OF URANIUM AND THORIUM CARBIDES WITH AQUEOUS SOLUTIONS OF HCl, H$sub 2$SO$sub 4$, NaOH, AND NH$sub 4$F.
10. U-Th RECOVERY FROM PYROLYTIC CARBON-COATED CARBIDE FUEL PARTICLES BY ELECTROLYSIS IN NITRIC ACID
11. METALLOGRAPHIC PREPARATION OF ARC-CAST THORIUM CARBIDES AND CORRELATION OF THEIR MICROSTRUCTURES WITH COMPOSITION.
12. COMBUSTION-DISSOLUTION EXPERIMENTS WITH IRRADIATED GRAPHITE-BASE REACTOR FUEL CONTAINING CARBON-COATED THORIUM-URANIUM DICARBIDE PARTICLES
13. PROCESSING OF BERYLLIUM OXIDE FUELS
14. HOT-CELL STUDIES OF AQUEOUS DISSOLUTION PROCESSES FOR IRRADIATED CARBIDE REACTOR FUELS
15. GRIND-LEACH PROCESS FOR GRAPHITE-BASE REACTOR FUELS THAT CONTAIN COATED PARTICLES: LABORATORY DEVELOPMENT.
16. Chemical Development Section B semiannual progress report, March 1, 1973 to August 31, 1973. Part I
17. REPROCESSING METHODS AND COSTS FOR SELECTED THORIUM-BEARING REACTOR FUEL TYPES
18. RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE FUELS. I. LABORATORY DEVELOPMENT OF A GRIND-LEACH PROCESS
19. Aqueous processes for uranium recovery from Rover fuel elements: laboratory development. Part III. Summary of the processes
20. DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I
21. THREE-MINUTE IRRADIATION AT VARIABLE POWER DENSITY OF PROTOTYPE CETR FUEL PELLETS
22. PROGRESS REPORT ON THE FLUOROX PROCESS FOR APRIL 30, 1957-JANUARY 14, 1958
23. OXIDATION AND CHLORINATION OF UO$sub 2$-PuO$sub 2$
24. PROCESSING OF URANIUM CARBIDE REACTOR FUELS. I. REACTION WITH WATER AND HCL
25. DEMONSTRATION OF THE ZIRFLEX PROCESS ON IRRADIATED PWR BLANKET FUEL
26. LABORATORY DEVELOPMENT OF THE SULFEX PROCESS FOR THE DISSOLUTION OF CONSOLIDATED EDISON POWER REACTOR FUEL
27. OFF-GASES FROM THE REACTIONS OF URANIUM CARBIDES WITH NITRIC ACID AT 90 C
28. AQUEOUS PROCESSING OF THORIUM FUELS, PART II
29. AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS
30. KINETICS OF THE THERMAL DECOMPOSITION OF URANYL FLUORIDE. I. PRELIMINARY RESULTS
31. AQUEOUS PROCESSING OF THORIUM FUELS
32. LABORATORY DEVELOPMENT OF THE FLUOROX PROCESS: II. THERMOGRAVIMETRIC STUDY OF THE CHEMICAL KINETICS FOR THE REACTION OF UF$sub 4$ WITH DRY OXYGEN
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