High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1980

Technical Report · Sat Aug 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/6134101· OSTI ID:6134101

Research activities are described concerning HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; HTR core evaluation; reactor physics; shielding; application and project assessments; and HTR Core Flow Test Loop studies.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6134101
• Report Number(s): ORNL-5753; ON: DE81029096; TRN: 81-015089
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COATED FUEL PARTICLES
FUEL RODS
HTGR TYPE REACTORS
PRESSURE VESSELS
REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
SHIELDING
ALLOY-HD-556
CORROSION
CREEP
DIFFUSION
GRAPHITE
HASTELLOY X
INCONEL 617
PHYSICAL RADIATION EFFECTS
PLUTONIUM
PRESTRESSED CONCRETE
RESEARCH PROGRAMS
SORPTIVE PROPERTIES
STEELS
TEST FACILITIES
WELDED JOINTS
ACTINIDES
ALLOYS
ALUMINIUM ALLOYS
BUILDING MATERIALS
CARBON
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COBALT ALLOYS
CONCRETES
CONTAINERS
ELEMENTS
FUEL ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HASTELLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
KINETICS
MANGANESE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NONMETALS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SURFACE PROPERTIES
TRANSURANIUM ELEMENTS
TUNGSTEN ALLOYS
210300* - Power Reactors
Nonbreeding
Graphite Moderated