Neutronics and thermal-hydraulics analysis of KUHFR

Neutronics and thermal-hydraulics analysis of KUHFR [electronic resource]

Detailed calculations have been completed for the KUHFR with MEU (45%) fuel. These results reflect the direct substitution of 45% enrichment UAl/sub x/-Al fuel at a density of 1.6 g/cm/sup 3/ uranium for the HEU (93%) fuel in the reference design. No other changes in the dimensions or design of the...

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Bibliographic Details
Online Access: Online Access
Main Authors: Mishima, K. (Author), Woodruff, W.L (Author)
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Argonne, Ill. : Oak Ridge, Tenn. : Argonne National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1980.
Subjects:
Kuhfr Reactor.
Reactor Cores.
Reactor Kinetics.
Burnup.
Fuel Cycle.
Fuel Management.
Heat Flux.
Heat Transfer.
Hydraulics.
Isotope Ratio.
Neutron Flux.
Temperature Distribution.
Energy Transfer.
Enriched Uranium Reactors.
Fluid Mechanics.
Irradiation Reactors.
Isotope Production Reactors.
Kinetics.
Mechanics.
Radiation Flux.
Reactor Components.
Reactors.
Research And Test Reactors.
Research Reactors.
Thermal Reactors.
Water Cooled Reactors.
Water Moderated Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-801144-11
E 1.99:conf-801144-11 Available

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