COMPONENTS OF THE FUSED-SALT AND SODIUM CIRCUITS OF THE AIRCRAFT REACTOR EXPERIMENT
The Aircraft Reactor Experiment (ARE) successfully demonstrated the feasibility of generating heat by fission in a fused-fluoride circulating fuel. Most of the heat was removed from the reactor by the fused fluoride at 1580 deg F. Sodium at 1350 deg F was used to cool the BeO moderator. With minor exceptions all the components proved to be adequate. The development of components and fabrication techaiques for this reactor consumed a four-year period, during which time the technology for handling high-temperatare fluids was extended to equipment operable above 1500 deg F. The methods used for determining compatibility of materials under static and dynamic conditions, standards for materials, and techniques for welding, fabrication, and assembly and the design criteria for pumps, seals, valves, heat exchangers, cold traps, expansion tanks, instrumentation, preheating devices, insulation, etc., are described. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-12-016694
- OSTI ID:
- 4308571
- Report Number(s):
- ORNL-2348
- Country of Publication:
- United States
- Language:
- English
Similar Records
LITERATURE SEARCH ON BEARING MATERIALS COMPATIBILITY WITH FUSED SALTS
AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 10, 1953
AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 10, 1953
Technical Report
·
Tue Dec 31 23:00:00 EST 1957
·
OSTI ID:4259785
AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 10, 1953
Technical Report
·
Wed Apr 15 23:00:00 EST 1953
·
OSTI ID:4080316
AIRCRAFT NUCLEAR PROPULSION PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 10, 1953
Technical Report
·
Wed Apr 15 23:00:00 EST 1953
·
OSTI ID:4745448
Related Subjects
AIRCRAFT
ARE
BERYLLIUM MODERATOR
BERYLLIUM OXIDES
COOLANT LOOPS
EVAPORATION
FABRICATION
FLUID FLOW
FLUORIDES
FUSED SALT FUEL
FUSED SALTS
HEAT EXCHANGERS
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
INSTRUMENTS
LIQUID METAL COOLANT
MATERIALS TESTING
MECHANICAL STRUCTURES
METALLURGY
PHYSICS
PLANNING
PUMPS
REACTOR CORE
REACTORS
SODIUM
STABILITY
STANDARDS
THERMAL INSULATION
THERMAL STRESSES
THERMODYNAMICS
VALVES
VESSELS
WELDING
ARE
BERYLLIUM MODERATOR
BERYLLIUM OXIDES
COOLANT LOOPS
EVAPORATION
FABRICATION
FLUID FLOW
FLUORIDES
FUSED SALT FUEL
FUSED SALTS
HEAT EXCHANGERS
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
INSTRUMENTS
LIQUID METAL COOLANT
MATERIALS TESTING
MECHANICAL STRUCTURES
METALLURGY
PHYSICS
PLANNING
PUMPS
REACTOR CORE
REACTORS
SODIUM
STABILITY
STANDARDS
THERMAL INSULATION
THERMAL STRESSES
THERMODYNAMICS
VALVES
VESSELS
WELDING