HTGR BASE PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING MAY 31, 1970.
- Research Organization:
- Gulf General Atomic, Inc., San Diego, Calif.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(04-3)-167
- NSA Number:
- NSA-24-043697
- OSTI ID:
- 4096511
- Report Number(s):
- GA--10088
- Country of Publication:
- United States
- Language:
- English
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COATED FUEL PARTICLES
COST
CREEP
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DIFFUSION
ECONOMICS
EXPANSION
FABRICATION
FISSION PRODUCTS
FUEL CYCLE
FUEL ELEMENTS
FUELS
GAS COOLED REACTORS
GRAPHITE
GRAPHITE/radiation effects on creep and dimensional stability of
neutron
HIGH-TEMPERATURE LATTICE TEST REACTOR/physics parameters of HTGR lattices in
(E)
HTGR TYPE REACTORS
IRRADIATION
LEACHING
MASS TRANSFER
N20510 --Chemistry--Radiochemistry & Nuclear Chemistry--Reactor Fuel Processing
N30250 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N38100* --Power Reactor Development
NEUTRONS
NEUTRONS/effects on graphite creep and dimensional stability
OXIDATION
PARTICLES
POWER REACTORS
RADIATION EFFECTS
REACTIVITY
REACTOR FUEL ELEMENTS/d
REACTOR FUEL ELEMENTS/reprocessing cycle development for gas cooled
REACTOR KINETICS
REACTORS
GAS-COOLED/development of 1000 MW(e) HTGR concept during March through May 1970
REACTORS
GAS-COOLED/fission product release and transport in high temperature
(E/T)
REACTORS
GAS-COOLED/fuel elements for high temperature
plant designs and costs for reprocessing
REACTORS
POWER/development of 1000 MW(e) HTGR concept during March through May 1970
REPROCESSING
STRONTIUM
STRONTIUM/diffusion in graphite
(E)
TESTING
THICKNESS
THORIUM OXIDES
THORIUM OXIDES ThO$sub 2$/ThO$sub 2$--UO$sub 2$
reprocessing of coated particle fuels of
fluid bed oxidation and leaching procedures in
(E)
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/ThO$sub 2$--UO$sub 2$
reprocessing of coated particle fuels of
fluid bed oxidation and leaching procedures in
(E)
COST
CREEP
DESIGN
DIFFUSION
ECONOMICS
EXPANSION
FABRICATION
FISSION PRODUCTS
FUEL CYCLE
FUEL ELEMENTS
FUELS
GAS COOLED REACTORS
GRAPHITE
GRAPHITE/radiation effects on creep and dimensional stability of
neutron
HIGH-TEMPERATURE LATTICE TEST REACTOR/physics parameters of HTGR lattices in
(E)
HTGR TYPE REACTORS
IRRADIATION
LEACHING
MASS TRANSFER
N20510 --Chemistry--Radiochemistry & Nuclear Chemistry--Reactor Fuel Processing
N30250 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N38100* --Power Reactor Development
NEUTRONS
NEUTRONS/effects on graphite creep and dimensional stability
OXIDATION
PARTICLES
POWER REACTORS
RADIATION EFFECTS
REACTIVITY
REACTOR FUEL ELEMENTS/d
REACTOR FUEL ELEMENTS/reprocessing cycle development for gas cooled
REACTOR KINETICS
REACTORS
GAS-COOLED/development of 1000 MW(e) HTGR concept during March through May 1970
REACTORS
GAS-COOLED/fission product release and transport in high temperature
(E/T)
REACTORS
GAS-COOLED/fuel elements for high temperature
plant designs and costs for reprocessing
REACTORS
POWER/development of 1000 MW(e) HTGR concept during March through May 1970
REPROCESSING
STRONTIUM
STRONTIUM/diffusion in graphite
(E)
TESTING
THICKNESS
THORIUM OXIDES
THORIUM OXIDES ThO$sub 2$/ThO$sub 2$--UO$sub 2$
reprocessing of coated particle fuels of
fluid bed oxidation and leaching procedures in
(E)
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/ThO$sub 2$--UO$sub 2$
reprocessing of coated particle fuels of
fluid bed oxidation and leaching procedures in
(E)