SYMPOSIA PAPER Published: 01 January 1994

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


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.

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West, CD
Oak Ridge National Laboratory, Oak Ridge, TN
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Developed by Committee: E10
Pages: 568–577
DOI: 10.1520/STP15152S
ISBN-EB: 978-0-8031-5281-6
ISBN-13: 978-0-8031-1899-7