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Impact of reduced-enrichment fuel on research reactor performance and utilization

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5317574
 [1]; ; ; ;
  1. Univ of Michigan, Ann Arbor
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None

OSTI ID:
5317574
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
COMPUTER CALCULATIONS
ENRICHED URANIUM REACTORS
FNR REACTOR
FUEL ELEMENTS
FUEL PLATES
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
MATHEMATICAL MODELS
POOL TYPE REACTORS
REACTIVITY COEFFICIENTS
REACTIVITY WORTHS
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