Status of HTGR technology development and demonstration

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5518116

Trauger, D B

Several HGTR items which require thorough testing include the core support and pads, vessel insulation and liner, and graphite fuel blocks. Tests which are to be conducted in the Component Flow Test Loop are discussed. The neutron streaming experiment at the Tower Shielding Facility is described. Materials and fuels development studies are also discussed. (DLC)

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5518116
• Report Number(s): CONF-830996-1; ON: DE84003310
• Resource Relation: Conference: Annual international conference on the high-temperature gas-cooled reactor, San Diego, CA, USA, 29 Sep 1983
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
RESEARCH PROGRAMS
COOLANT LOOPS
GRAPHITE
MATERIALS TESTING
NUCLEAR FUELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR VESSELS
REVIEWS
SUPPORTS
TSR-1 REACTOR
TSR-2 REACTOR
CARBON
CONTAINERS
COOLING SYSTEMS
DOCUMENT TYPES
ELEMENTAL MINERALS
ELEMENTS
ENERGY SOURCES
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS
MECHANICAL STRUCTURES
MINERALS
NONMETALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated