STP1228

    Dosimetry Issues for an Ultra-High Flux Beam and Multipurpose Research Reactor Design

    Published: Jan 1994


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    Abstract

    The Advanced Neutron Source is a new user facility for all fields of neutron research, including neutron beam experiments, materials analysis, materials testing, and isotope production. The complement and layout of the experimental facilities have been determined sufficiently, at a conceptual design level, to make reliable cost and schedule estimates. The source of neutrons will be a heavy water reactor, constructed largely of aluminum, with an available thermal neutron flux 5–10 times higher than existing research reactors.

    Among the dosimetry issues to be faced are damage prediction and surveillance for component life attainment; measurement of fluence and spectra in regions where both change substantially over a distance of a few centimeters; and characterization and measurement of the radiation field in the research areas around the neutron beam experiments.

    Keywords:

    dosimetry, ultra-high flux beam, research reactor, neutron research


    Author Information:

    West, CD
    Project director, Oak Ridge National Laboratory, Oak Ridge, TN


    Paper ID: STP15152S

    Committee/Subcommittee: E10.01

    DOI: 10.1520/STP15152S


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