67 results on '"Ferris L"'
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2. Component Performance of J71-A-2(600-D1) Turbojet Engine at Several Reynolds Number Indices
3. Full-scale, free-jet investigation of methods of improving outlet flow distribution in a side-inlet supersonic diffuser
4. Starting and Performance Characteristics of a Large Asymmetric Supersonic Free-jet Facility
5. Criterions for Condensation-free Flow in Supersonic Tunnels
6. Criterions for condensation-free flow in supersonic tunnels
7. Design Data for Graphical Construction of Two-Dimensional Sharp-Edge-Throat Supersonic Nozzles
8. Burn-leach process for recovery of uranium from Rover fuel: terminal report of laboratory development
9. EXPERIMENTAL SURVEY OF CLOSE-COUPLED PROCESSING METHODS FOR FUELS CONTAINING URANIUM AND THORIUM
10. DECLADDING OF PWR BLANKET FUEL ELEMENTS WITH AQUEOUS AMMONIUM FLUORIDE SOLUTIONS
11. SAFETY, HEALTH PHYSICS, AND OPERATING PROCEDURES FOR CHEMICAL TECHNOLOGY DIVISION BERYLLIUM FACILITY
12. ESTIMATED BEHAVIOR OF TITANIUM IN MSBR CHEMICAL PROCESSING SYSTEMS.
13. LIQUID--VAPOR EQUILIBRIA IN LiF--BeF$sub 2$ AND LiF--BeF$sub 2$--ThF$sub 4$ SYSTEMS.
14. CHEMICAL TECHNOLOGY DIVISION ZIRFLEX PROCESS FOR PWR BLANKET FUEL. II. REVISED FLOWSHEET
15. BALL-MILLING OF GRAPHITE-BASE REACTOR FUEL
16. 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.
17. U-Th RECOVERY FROM PYROLYTIC CARBON-COATED CARBIDE FUEL PARTICLES BY ELECTROLYSIS IN NITRIC ACID
18. METALLOGRAPHIC PREPARATION OF ARC-CAST THORIUM CARBIDES AND CORRELATION OF THEIR MICROSTRUCTURES WITH COMPOSITION.
19. COMBUSTION-DISSOLUTION EXPERIMENTS WITH IRRADIATED GRAPHITE-BASE REACTOR FUEL CONTAINING CARBON-COATED THORIUM-URANIUM DICARBIDE PARTICLES
20. PROCESSING OF BERYLLIUM OXIDE FUELS
21. HOT-CELL STUDIES OF AQUEOUS DISSOLUTION PROCESSES FOR IRRADIATED CARBIDE REACTOR FUELS
22. GRIND-LEACH PROCESS FOR GRAPHITE-BASE REACTOR FUELS THAT CONTAIN COATED PARTICLES: LABORATORY DEVELOPMENT.
23. Chemical Development Section B semiannual progress report, March 1, 1973 to August 31, 1973. Part I
24. REPROCESSING METHODS AND COSTS FOR SELECTED THORIUM-BEARING REACTOR FUEL TYPES
25. RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE FUELS. I. LABORATORY DEVELOPMENT OF A GRIND-LEACH PROCESS
26. Aqueous processes for uranium recovery from Rover fuel elements: laboratory development. Part III. Summary of the processes
27. DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I
28. THREE-MINUTE IRRADIATION AT VARIABLE POWER DENSITY OF PROTOTYPE CETR FUEL PELLETS
29. PROGRESS REPORT ON THE FLUOROX PROCESS FOR APRIL 30, 1957-JANUARY 14, 1958
30. OXIDATION AND CHLORINATION OF UO$sub 2$-PuO$sub 2$
31. PROCESSING OF URANIUM CARBIDE REACTOR FUELS. I. REACTION WITH WATER AND HCL
32. DEMONSTRATION OF THE ZIRFLEX PROCESS ON IRRADIATED PWR BLANKET FUEL
33. LABORATORY DEVELOPMENT OF THE SULFEX PROCESS FOR THE DISSOLUTION OF CONSOLIDATED EDISON POWER REACTOR FUEL
34. OFF-GASES FROM THE REACTIONS OF URANIUM CARBIDES WITH NITRIC ACID AT 90 C
35. AQUEOUS PROCESSING OF THORIUM FUELS, PART II
36. AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS
37. KINETICS OF THE THERMAL DECOMPOSITION OF URANYL FLUORIDE. I. PRELIMINARY RESULTS
38. AQUEOUS PROCESSING OF THORIUM FUELS
39. LABORATORY DEVELOPMENT OF THE FLUOROX PROCESS: II. THERMOGRAVIMETRIC STUDY OF THE CHEMICAL KINETICS FOR THE REACTION OF UF$sub 4$ WITH DRY OXYGEN
40. CHEMICAL PROCESSING OF COATED PARTICLE FUELS
41. GRIND-LEACH PROCESS FOR GRAPHITE-BASE REACTOR FUELS THAT CONTAIN COATED PARTICLES: LABORATORY DEVELOPMENT.
42. Burn-leach process for recovery of uranium from Rover fuel: terminal report of laboratory development
43. DECLADDING OF PWR BLANKET FUEL ELEMENTS WITH AQUEOUS AMMONIUM FLUORIDE SOLUTIONS
44. EXPLOSION OF EBWR ALLOY IN BOILING CONCENTRATED NITRIC ACID
45. 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.
46. U-Th RECOVERY FROM PYROLYTIC CARBON-COATED CARBIDE FUEL PARTICLES BY ELECTROLYSIS IN NITRIC ACID
47. BALL-MILLING OF GRAPHITE-BASE REACTOR FUEL
48. EXPERIMENTAL SURVEY OF CLOSE-COUPLED PROCESSING METHODS FOR FUELS CONTAINING URANIUM AND THORIUM
49. DEMONSTRATION OF THE ZIRFLEX PROCESS ON IRRADIATED PWR BLANKET FUEL
50. OXIDATION AND CHLORINATION OF UO$sub 2$-PuO$sub 2$
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