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Equilibrium code calculations for the Ford Nuclear Reactor with reduced enrichment fuel

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5225147

None

Research Organization:
Argonne National Lab., IL
OSTI ID:
5225147
Report Number(s):
CONF-791103-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 33; ISSN TANSA
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BURNUP
ENRICHED URANIUM REACTORS
FNR REACTOR
FUEL ELEMENTS
FUEL PLATES
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
POOL TYPE REACTORS
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TEST REACTORS
THERMAL REACTORS
TRAINING REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS