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    Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor


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    Yankee Atomic Electric Company undertook a Test Irradiation Program at the Ford Nuclear Reactor of the University of Michigan. The program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials. The program was also intended to remove uncertainties in the existing reactor vessel fluence and damage predictions on the Yankee Rowe reactor vessel steel. Since this is the first in-core experiment of this type for the Ford Nuclear Reactor, the measurement of the reaction rate and the estimate of the fluence are presented.


    neutron dosimetry, neutron spectrum calculations, neutron transport, test reactor irradiations

    Author Information:

    Cacciapouti, RJ
    Manager, Reactor Physics, Yankee Atomic Electric Company, Bolton, Ma

    Petrusha, L
    Davis-Besse Resident Engineer, B&W Nuclear Technologies, Lynchburg, VA

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP15158S