HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1976. [Graphite and fuel irradiation; fission product release]
The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and, where appropriate, the data are presented in tables, graphs, and photographs.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- E(04-3)-0167-PRJ-17
- OSTI ID:
- 7125545
- Report Number(s):
- GA-A-14046
- Country of Publication:
- United States
- Language:
- English
Similar Records
HTGR fuels and core development program. Quarterly progress report for the period ending May 31, 1976. [Graphite and fuels irradiation; fission product release]
HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1976. [Graphite and fuel irradiations; fission product release]
HTGR fuels and core development program. Quarterly progress report for period ending February 29, 1976. [Graphite and fuel irradiation; fission product release]
Technical Report
·
Wed Jun 30 00:00:00 EDT 1976
·
OSTI ID:7357586
HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1976. [Graphite and fuel irradiations; fission product release]
Technical Report
·
Sun Dec 26 23:00:00 EST 1976
·
OSTI ID:7225284
HTGR fuels and core development program. Quarterly progress report for period ending February 29, 1976. [Graphite and fuel irradiation; fission product release]
Technical Report
·
Tue Mar 30 23:00:00 EST 1976
·
OSTI ID:7365684
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
360605 -- Materials-- Radiation Effects
ACTINIDE COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
DIFFUSION
ELEMENTS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
TENSILE PROPERTIES
TESTING
THORIUM CARBIDES
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
360605 -- Materials-- Radiation Effects
ACTINIDE COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
DIFFUSION
ELEMENTS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
TENSILE PROPERTIES
TESTING
THORIUM CARBIDES
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES