AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 10, 1952
Analysis of the circulating fuel aircraft reactor was extended to systems incorporating intermediate heat exchangers, various secondary coolants, liquid moderators, core is discussed. Progress is reported in the design of the reactor, fluid circuits, the reactor building, and associated equipment. Development of plumbing for high-temperature fluoride mixtures is reported. Techniques of preparation, purification, and handling fluoride mixtures were investigated. Techniques of pumping, sealing, and controlling fluoride coolants were developed along with lubrication methods. Criticallty studies for the ARE, the ANP, and the simulated General Electric direct-cycle reactor are reported. Angular and energy-dependent radiation measurements on the mockup of the divided shield are discussed. Research on ducts included detailed measurement of the effect of duct geometry on neutron transmission, and confirmation of a neutron transmission theory for ducts. Design details of the Tower Shielding Facility are presented. Additional cross-section measurements were obtained on the 5-Mev Van de Graaff and the time-of-flight neutron spectrometer for use in reactor cross-section determinations. Measurements of the total cross section of Fe were made at 0.7 to 3.6 Mev. Research on high-temperature liquids for use as a fuel- coolant for the circulating-fuel reactor is discussed. Several fluoride systems are being investigated. Tests of fluoride, hydroxide, and liquid metal corrosion are reported. The effect of various additives on fluoride and hydroxide corrosion is being evaluated. Investigation of metallurgical processes involved in the construction and assembly of a high-temperature reactor core is reported. Information on fabrication of control rods, welding and brazing of core structure, and creep and stress-rupture of metals is presented along with data on viscosity, thermal conductivity, heat capacity, and vapor pressure ot fluoride mixtures. Results of a theoretical analysis of heat transfer in circulating-fuel reactors were used to establish the design parameters for the core fuel circuit. Mathematical expressions for natural convection associated with liquid fuels were developed for the case of turbulent flow. Data on the heat transfer of boiling Hg is included. Radiation damage studies included those on fuel capsules, inpile liquid loops, and creep and thermal conductivity in metals. A summary of findings from a survey of the supercriticalwater reactor is included. Procedures for the analysis of fluoride mixtures for corrosion products and changes in composition are reported. (J.R.D.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-16-034072
- OSTI ID:
- 4776410
- Report Number(s):
- ORNL-1227
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ARE
BOILING
BRAZING
BUILDINGS
CAPSULES
CONTROL ELEMENTS
COOLANT LOOPS
CORROSION
CREEP
CRITICALITY
CROSS SECTIONS
ENERGY
ENERGY RANGE
EQUATIONS
FABRICATION
FAILURES
FAST NEUTRONS
FLUID FLOW
FLUORIDES
FUEL SLURRIES
FUEL SOLUTIONS
FUSED SALT FUEL
HEAT EXCHANGERS
HEAT TRANSFER
HIGH TEMPERATURE
HYDROXIDES
IMPURITIES
IN PILE LOOPS
IRON
IRRADIATION
LIQUID FLOW
LIQUIDS
LUBRICATION
MEASURED VALUES
MECHANICAL STRUCTURES
MERCURY
METALLURGY
MIXING
MOCKUP
MODERATORS
NEUTRON BEAMS
NEUTRON SPECTROMETERS
PLANNING
PREPARATION
PRESSURE
PROPULSION
PUMPS
QUANTITY RATIO
RADIATION DOSES
RADIATION EFFECTS
REACTOR TECHNOLOGY