Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal

Technical Report · Tue Jan 01 04:00:00 EST 1980

DOI:https://doi.org/10.2172/1130757· OSTI ID:1130757

De Volpi, A. ^[1]; Fink, C. L. ^[1]; Marsh, G. E. ^[1]; Rhodes, E. A. ^[1]; Stanford, G. S. ^[1]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States)

Fuel-motion surveillance using the fast-neutron hodoscope in TREAT experiments has advanced from an initial role of providing time/location/velocity data to that of offering quantitative mass results. The material and radiation surroundings of the test section contribute to intrinsic and instrumental effects upon hodoscope detectors that require detailed corrections. Depending upon the experiment, count rate compensation is usually required for deadtime, power level, nonlinear response, efficiency, background, and detector calibration. Depending on their magnitude and amenability to analytical and empirical treatment, systematic corrections may be needed for self-shielding, self-multiplication, self-attenuation, flux depression, and other effects. Current verified hodoscope response (for 1- to 7-pin fuel bundles) may be paramatrically characterized under optimum conditions by 1-ms time resolution; 0.25-mm lateral and 5-mm axial-motion displacement resolution; and 50-mg single-pin mass resolution. The experimental and theoretical foundation for this performance is given, with particular emphasis on the geometrical response function and the statistical limits of fuel-motion resolution. Comparisons are made with alternative diagnostic systems.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1130757
• Report Number(s): ANL/RAS--80-17
• Country of Publication: United States
• Language: English

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