LMFBR FUEL CYCLE STUDIES PROGRESS REPORT FOR JANUARY 1970, NO. 11.
- Published
- United States : [publisher not identified], 1970.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1970. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Report Numbers
- ORNL-TM-2871
- Other Subject(s)
- Fabrication
- Fbr type reactors
- Fission products
- Fission products/release in reprocessing of lmfbr fuels
- Head end processes
- Iodine
- Iodine/release in reprocessing of lmfbr fuels
- Liquid metal cooled reactors
- Materials testing
- N40450 -chemistry-radiochemistry & nuclear chemistry- reactor fuel processing
- N50220 -metals, ceramics, & other materials-metals & alloys-preparation & fabrication
- Nuclear fuels
- Plutonium carbides/puc- uc, preparation by sol-gel process
- Plutonium nitrates
- Plutonium nitrates/conversion to oxide in lmfbr fuel cycle
- Plutonium oxides puo2/ preparation of.
- Plutonium oxides puo2/puo2-uo2, preparation of microspheres of, by cusp-apex mixed sol process
- Plutonium oxides
- Plutonium
- Plutonium/ separation from spent oxide fuels by solvent extraction using tbp
- Plutonium/reduction of hexavalent to tetravalent, using nitric oxide gas
- Purex process
- Purex process/flowsheet development for lmfbr fuels
- Reactor fuels/reprocessing of oxide, continuous dissolution in.
- Reprocessing
- Separation processes
- Sol-gel process
- Sol-gel process/development for lmfbr fuel recycle
- Spent fuels
- Transport
- Uranium carbides/puc-uc, preparation by sol-gel process
- Uranium dioxide
- Uranium oxides uo2/preparation of sols of.
- Uranium oxides uo2/puo2-uo2, preparation of microspheres of, by cusp-apex mixed sol process
- Uranium
- Uranium/ separation from spent oxide fuels by solvent extraction using tbp
- Volatility
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: W-7405-ENG-26
NSA number: NSA-26-045406
OSTI Identifier 4626371
Research organization: Oak Ridge National Lab., Tenn.
View MARC record | catkey: 46150370