Gas-cooled reactor programs: high-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1981

Technical Report · Tue Jun 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/5341307· OSTI ID:5341307

Information is presented concerning HTGR chemistry; fueled graphite development; irradiation services for General Atomic Company; prestressed concrete pressure vessel development; HTGR structural materials; graphite development; high-temperature reactor physics studies; shielding studies; component flow test loop studies; core support performance test; and application and project assessments.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5341307
• Report Number(s): ORNL-5871; ON: DE82016577; TRN: 82-013260
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR MATERIALS
RESEARCH PROGRAMS
COATED FUEL PARTICLES
CREEP
FRACTURE PROPERTIES
GRAPHITE
HASTELLOY X
MICROSTRUCTURE
OXIDATION
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
SHIELDING
TEST FACILITIES
URANIUM CARBIDES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COBALT ALLOYS
CONTAINERS
COOLING SYSTEMS
CRYSTAL STRUCTURE
ELEMENTAL MINERALS
ELEMENTS
ENERGY SYSTEMS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HASTELLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
KINETICS
MATERIALS
MECHANICAL PROPERTIES
MINERALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
REACTOR COOLING SYSTEMS
REACTORS
TUNGSTEN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
210300* - Power Reactors
Nonbreeding
Graphite Moderated