Chemical behavior and improved retention of fission products in irradiated HTGR fuels
Conference
·
OSTI ID:4178149
- Research Organization:
- Kernforschungsanlage, Juelich, Ger.
- NSA Number:
- NSA-32-030185
- OSTI ID:
- 4178149
- Report Number(s):
- CONF-741030-P1
- Resource Relation:
- Conference: Symposium on thermodynamics of nuclear materials, Vienna, Austria, 21 Oct 1974; Other Information: See STI/PUB--380(Vol.1); CONF-741030--P1. Orig. Receipt Date: 31-DEC-75; Related Information: Thermodynamics of nuclear materials, 1974. Volume I
- Country of Publication:
- Austria
- Language:
- English
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Related Subjects
N77300* -Reactors-Power Reactors
Non-breeding
Graphite Moderated
N50140 -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
210300* -Nuclear Power Plants-Power Reactors
Non- Breeding
Graphite Moderated
*COATED FUEL PARTICLES- FISSION PRODUCT RELEASE
*FISSION PRODUCTS- CHEMICAL REACTIONS
*HTGR TYPE REACTORS- COATED FUEL PARTICLES
*THORIUM OXIDES- PHYSICAL RADIATION EFFECTS
*URANIUM CARBIDES- PHYSICAL RADIATION EFFECTS
*URANIUM DIOXIDE- PHYSICAL RADIATION EFFECTS
ANNEALING
BURNUP
CONTAINMENT
FUEL ELEMENTS
GASES
GETTERING
PYROLYTIC CARBON
Non-breeding
Graphite Moderated
N50140 -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
210300* -Nuclear Power Plants-Power Reactors
Non- Breeding
Graphite Moderated
*COATED FUEL PARTICLES- FISSION PRODUCT RELEASE
*FISSION PRODUCTS- CHEMICAL REACTIONS
*HTGR TYPE REACTORS- COATED FUEL PARTICLES
*THORIUM OXIDES- PHYSICAL RADIATION EFFECTS
*URANIUM CARBIDES- PHYSICAL RADIATION EFFECTS
*URANIUM DIOXIDE- PHYSICAL RADIATION EFFECTS
ANNEALING
BURNUP
CONTAINMENT
FUEL ELEMENTS
GASES
GETTERING
PYROLYTIC CARBON