HTGR Generic Technology Program. Semiannual report for the period ending September 30, 1979

Technical Report · Thu Nov 01 00:00:00 EST 1979

DOI:https://doi.org/10.2172/5750199· OSTI ID:5750199

The technical accomplishments on the HTGR Generic Technology Program at General Atomic during the second half of FY-79 are reported. The report covers a period when the major design direction of the National HTGR Program is in the process of changing from the HTGR-SC emphasis to an HTGR-GT emphasis in the near term. The HTGR Generic Technology Program activities have been redirected to ensure that the tasks covered are supportive of this changing emphasis in HTGR applications. The activities include the need to develop an MEU fuel, and the need to qualify materials and components for the higher temperatures of the gas turbine plant.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: AT03-76ET35300
• OSTI ID: 5750199
• Report Number(s): GA-A-15606; TRN: 80-003119
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR SAFETY
RESEARCH PROGRAMS
COATED FUEL PARTICLES
CREEP
FABRICATION
FISSION PRODUCTS
FUEL ELEMENTS
GRAPHITE
OXIDATION
PERFORMANCE TESTING
PRIMARY COOLANT CIRCUITS
REACTOR INTERNALS
REACTOR OPERATION
RISK ASSESSMENT
THERMAL STRESSES
VRAIN REACTOR
CARBON
CHEMICAL REACTIONS
COOLING SYSTEMS
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
ISOTOPES
MECHANICAL PROPERTIES
NONMETALS
OPERATION
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
STRESSES
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated