TURRET: A HIGH TEMPERATURE GAS-CYCLE REACTOR PROPOSAL
A nitrogen-cooled graphite-moderated nuclear reactor experiment is proposed to drive a closed-cycle gas turbine power plant at 1300 deg F. The annular core of the reactor can be rotated inside the reflector to permit fuel loading and discharge while operating at full power. Small cylindrical fuel elements of graphite are solutionimpregnated with partially enriched uranium. The fuel is recycled by incineration of the elements, chemical fresh graphite tn a small batch process. The unclad, uncoated fuel should permit high burn-up and simple fuel processing, but allows fission product diffusion into the gas stream. While methods are proposed for the removal of these from the gas, the Song-term consequences on turbine operation are unknown. The compatibility of nitrogen gas with the fuel has been studied experimentally. The radial movement of fuel gives a reactor with a constant power profile and no excess reactivity. The temperature is regulated by the fuel charging rate. (auth)
- Research Organization:
- Los Alamos Scientific Lab., N. Mex.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-12-010074
- OSTI ID:
- 4336875
- Report Number(s):
- LA-2198
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CANNING
CHEMICAL REACTIONS
CORROSION
ENRICHMENT
FISSION PRODUCTS
FUEL ELEMENTS
FUELS
GAS COOLANT
GRAPHITE MODERATOR
HIGH TEMPERATURE
MECHANICAL STRUCTURES
MOTION
NITROGEN
PHYSICS
PLANNING
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTORS
REFLECTORS
REPROCESSING
SEPARATION PROCESSES
STABILITY
TEMPERATURE
TURBINES
TURRET
UHTREX
URANIUM