Comparative performance of a 10-MW generic reactor with HEU and LEU fuels
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6662703
None
- Research Organization:
- ANL, Argonne, IL 60439
- OSTI ID:
- 6662703
- Report Number(s):
- CONF-801107-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 35
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
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ACTINIDES
BURNUP
ELEMENTS
ENRICHED URANIUM
FUEL ELEMENTS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NEUTRON FLUX
OPERATION
PERFORMANCE TESTING
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REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
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RESEARCH AND TEST REACTORS
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220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BURNUP
ELEMENTS
ENRICHED URANIUM
FUEL ELEMENTS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NEUTRON FLUX
OPERATION
PERFORMANCE TESTING
RADIATION FLUX
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REACTOR CORES
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SLIGHTLY ENRICHED URANIUM
TESTING
URANIUM