DETERMINATION OF OXIDE FUEL TEMPERATURE PROFILES
- Author
- Christensen, J. A.
- Published
- United States : [publisher not identified], 1966.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1966. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Report Numbers
- BNWL-CC-604
- Other Subject(s)
- Fuels
- N38550 -research & test reactors & critical assemblies- fuels
- Pellets
- Plutonium oxides puo2/puo2-uo2, fuel temperature profile of powder and pellet, calculation of prtr
- Plutonium oxides
- Plutonium recycle test reactor/fuel temperature profiles for, calculation of uranium oxide (uo2) and plutonium oxide (puo2)-uranium oxide (uo ).
- Powders
- Prtr
- Reactor fuels/temperature profiles for prtr powder and pellet uranium oxide (uo2) and plutonium oxide (puo2)-uranium oxide (uo2), calculation of.
- Research reactors
- Temperature
- Thermal conductivity
- Uranium dioxide
- Uranium oxides uo2/puo2- uo2, fuel temperature profile of powder and pellet, calculation of prtr
- Uranium oxides uo2/temperature profiles in powder and pellet fuels of, calculation of.
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(45-1)-1830
NSA number: NSA-23-007396
OSTI Identifier 4816696
Research organization: Battelle-Northwest, Richland, Wash. Pacific Northwest Lab.
View MARC record | catkey: 42542820