Gas-cooled reactor programs: High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1979

Technical Report · Tue Jul 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5353796· OSTI ID:5353796

Progress in HTGR studies is reported in the following areas: HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; and evaluation of the pebble-bed HTR.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5353796
• Report Number(s): ORNL-5643; TRN: 80-012317
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
HTGR TYPE REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
RESEARCH PROGRAMS
ANNEALING
BURNUP
COATED FUEL PARTICLES
CORROSION
FATIGUE
GRAPHITE
MECHANICAL PROPERTIES
MICROSTRUCTURE
PEBBLE BED REACTORS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTOR CORES
REACTOR KINETICS
STEAM
THORIUM OXIDES
URANIUM CARBIDES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
BUILDING MATERIALS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
CONCRETES
CONTAINERS
CRYSTAL STRUCTURE
ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TREATMENTS
HOMOGENEOUS REACTORS
KINETICS
MATERIALS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RADIATION EFFECTS
REACTORS
SOLID HOMOGENEOUS REACTORS
TESTING
THORIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
210300* - Power Reactors
Nonbreeding
Graphite Moderated
360603 - Materials- Properties
360206 - Ceramics
Cermets
& Refractories- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties