AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 10, 1952

Technical Report · Fri Aug 01 00:00:00 EDT 1952

DOI:https://doi.org/10.2172/4782915· OSTI ID:4782915

Cottrell, W.B. ed.

7 A 9 8 ; < @ G 7 : 8 8 < 7 9 rporating intermediate heat exchangers led to the use of a spherical-shell type of heat exchanger and shield arrangement; a diagram of such a heat-exchanger arrangement is shown. A design study was undertaken of a circulating-fluoride-fuel reactor core in which a thick reflector replaces the moderator. Minor modifications were made in the design of the aircraft Reactor Experiment to be constructed at ORNL; the changes made during the last quarter and the progress made in detailing the system and procuring outside manufactured components are discussed, as well as a procedure that was outlined for the operation of the reactor. Brief descriptions of pumps and valves which were operated successfully with molten fluoride mixtures for extended periods of time at 1500 F are given. NaK-toNaK and Na- to-air heat exchangers were operated for long periods. Efforts devoted to developing instruments for flow, pressure, liquid-level, and control of the ARE and experimental high-temperature-liquid systems are reported. Techniques are discussed for the manufacture, transfer, and loading of fluoride mixtures without contamination. Studies of the circulating-fuel aircraft reactor led to the conclusion that power oscillations in this system are strongly dampened by a mechanism associated with the circulation of the fuel. A critical assembly of the box-type, direct-cycle reactor, was investigated for the GE-ANP program; fission rate, flux measurements, reflector effects, and temperature responsc were determined. A resume of the results from an earlier series of experiments with a graphite-moderated reactor is also presented. Measurements of the energy and angular distribution of gamma radiation from the divided-shield mockup around the Bulk Shielding Reactor were continued; the spectrometer positions for the measurements are listed, and a graph shows spectra at various distances from the reactor with and without the divided-shield mock-up. In another experiment with this reactor, the effect of radiation from the side of the reactor shield that scatters in air and penetrates the crew compartment was measured. The albedo of neutrons and gamma rays on concrete was determined with artificial sources to facilitate calculations for the Tower Shielding Facllity. A series of short experiments on the gamma radiation attenuation of Fe and Pb in regions close to the source were completed in the Lid Tank. The results of the gamma-attenuation measurements are presented graphically for 63% Fe - 37% water; 63% Fe -- 37% borated water; solid Fe thermal shield in water; and solid Pb shadow shields in water. The air-duct research in the Lid Tank and Thermal Column Facilities has continued. The Lid Tank research was concentrated on large-scale mockups of annular designs, and the Thermal Column work was devoted to a series of experiments to provide a better understanding or the important atienuation processes. The total neutron cross section measurements of Li/sup 6/ show only one resonance, which is at 270 kv. The research on hightemperature liquids was mostly devoted to the development of a satisfactory fluoride fuel for the ARE. The phase diagrams of several binary, ternary, and quaternary fluoride systems were examined. Tentative phase diagrams are presented of two- and three- component fluoride systems containing Rb, Na, K, and ZrF/sub 4/; these studies were undertaken to determine the coolant and fuel-solvent possibilities of the systems. The corrosion-research effort was divided among static and dynamic tests of fluorides, hydroxides, and liquid metals. Tests showed that small additions of Na, K, Mn, and Ca are beneficial in minimizing fiuoride corrosion. Various fluoride mixtures were circulated in thermal convection loops. Stainless steel loops generally plug after short periods, whereas Inconel loops consistently operate up to 1000 hours. In the study of the reaction products of

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-16-034073
• OSTI ID: 4782915
• Report Number(s): ORNL-1294
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ABSORPTION
AIR
AIRCRAFT
ALUMINUM ALLOYS
ALUMINUM OXIDES
ANGULAR DISTRIBUTION
ARE
BERYLLIUM
BORON CARBIDES
BORON COMPOUNDS
BRAZING
CALCIUM
CAPSULES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COMPACTING
CONCRETES
CONFIGURATION
CONTAMINATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
COOLANTS
CORROSION
CREEP
CRITICAL ASSEMBLIES
CROSS SECTIONS
DENSITY
DIAGRAMS
DISTRIBUTION
EQUATIONS
EUTECTICS
FABRICATION
FLUORIDES
FUEL ELEMENTS
FUEL SLURRIES
FUEL SOLUTIONS
FUELS
FUSED SALT FUEL
GAMMA RADIATION
GRAPHITE MODERATOR
HEAT EXCHANGERS
HIGH TEMPERATURE
INCONEL ALLOYS
INSTRUMENTS
IRON
IRRADIATION
LEAD
LEVELS
LI