PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1961

Technical Report · Wed Feb 01 04:00:00 EST 1961

OSTI ID:4013753

Dayton, R W; Tipton, Jr, C R

Work is reported on studies of: reactor materials and components; fuels; fuel element development; gas-pressure bonding of ceramic, cermet, and dispersion fuel elements; uranium carbide; growth of UO/sub 2/ crystals; radioisotope and radiation applications; void distribution and heat transfer; uranium mononitride; materials development and evaluation; coated-particle fuel materials; recovery of spent fuel elements; evaluation of fueled-graphite elements for pebblebed reactors; fabrication processes for cold bonding Zircaloy-2 to type 410 stainless steel; radiation effects on fuel materials for MGCR; irradiation of SM-2 fuels; gascooled reactors; corrosion of thorium and uranium under storage conditions; and gas-pressure bonding of berylliumclad fuel elements. (B.O.G.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-15-017876
• OSTI ID: 4013753
• Report Number(s): BMI-1496
• Country of Publication: United States
• Language: English

Related Subjects

BERYLLIUM
BONDING
BUBBLES
BURNUP
CERAMICS
CERMETS
COATING
COOLANTS
CORROSION
CRYSTALLIZATION
CRYSTALS
DISPERSIONS
DISTRIBUTION
FABRICATION
FUEL ELEMENTS
FUELS
GAS COOLANT
GASES
GENERAL AND MISCELLANEOUS
GRAPHITE
HEAT TRANSFER
IRRADIATION
MGCR
MODERATORS
PARTICLES
PEBBLE BED
PELLETS
PLANNING
PRESSURE
RADIATION EFFECTS
RADIATIONS
RADIOISOTOPES
REACTORS
RECOVERY
REFLECTORS
SM-2
STAINLESS STEELS
STORAGE
THORIUM
URANIUM
URANIUM CARBIDES
URANIUM DIOXIDE
URANIUM NITRIDES
USES
ZIRCALOY