HTGR Base Program. Quarterly progress report for the period ending November 30, 1973
The High-Temperature Gas-cooled Reactor (HTGR) work reported includes studies of basic fission-product distribution mechanisms, recycle fuel studies (including designing and testing of recycle test elements) and exploration of head-end reprocessing methods (as part of a national recycle plan and of a recycle fuel plan), and physics and fuel management studies. Materials studies include irradiation and analysis of fuel particles in capsules to evaluate fuel systems, and basic studies of control materials and of carbon and graphite. Experimental procedures and results are discussed and, where appropriate, the data are presented. (auth)
- Research Organization:
- Gulf General Atomic Co., San Diego, Calif. (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(04-3)-167
- NSA Number:
- NSA-29-020032
- OSTI ID:
- 4353413
- Report Number(s):
- GULF-GA-A--12818
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*HTGR TYPE REACTORS-- RESEARCH PROGRAMS CESIUM 137-- F CODES-- FISSION PRODUCTS-- FUEL ELEMENTS-- PRIMARY COOLANT CIRCUITS-- SPATIAL DISTRIBUTION
COATED FUEL PARTICLES- - COMBUSTION-- CRUSHING-- FUEL CYCLE-- HEAD END PROCESSES-- LEACHING-- REPROCESSING-- SEPARATION PROCESSES
COATED FUEL PARTICLES-- IRRADIATION-- PHYSICAL RADIATION EFFECTS-- THORIUM OXIDES-- URANIUM DIOXIDE
GRAPHITE-- HELIUM-- OXIDATION-- STEAM
GRAPHITE-- PHYSICAL RADIATION EFFECTS-- TENSILE PROPERTIES
N40450 --Chemistry--Radiochemistry & Nuclear Chemistry--Reactor Fuel Processing
N50140 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N50300 --Metals
Ceramics
& Other Materials--Plastics & Other Materials
N77300* --Reactors--Power Reactors
Non-breeding
Graphite Moderated
COATED FUEL PARTICLES- - COMBUSTION-- CRUSHING-- FUEL CYCLE-- HEAD END PROCESSES-- LEACHING-- REPROCESSING-- SEPARATION PROCESSES
COATED FUEL PARTICLES-- IRRADIATION-- PHYSICAL RADIATION EFFECTS-- THORIUM OXIDES-- URANIUM DIOXIDE
GRAPHITE-- HELIUM-- OXIDATION-- STEAM
GRAPHITE-- PHYSICAL RADIATION EFFECTS-- TENSILE PROPERTIES
N40450 --Chemistry--Radiochemistry & Nuclear Chemistry--Reactor Fuel Processing
N50140 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N50300 --Metals
Ceramics
& Other Materials--Plastics & Other Materials
N77300* --Reactors--Power Reactors
Non-breeding
Graphite Moderated