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Generic study of research reactor fuel element loadings with reduced uranium enrichments

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5225167
;

None

Research Organization:
Argonne National Lab., IL
OSTI ID:
5225167
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
FUEL CYCLE
FUEL ELEMENTS
ISOTOPE SEPARATION
KINETICS
REACTIVITY COEFFICIENTS
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SEPARATION PROCESSES