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A methodological concept is developed to determine the burnup of certain neutron flux monitors in an unknown, intense reactor neutron field. In particular, it is shown how to evaluate the burnup effects involved in the neutron activation of (197)Au prior to any neutron flux characterization , based merely on the spectrometry of the (198)Au and (199)Au decay gamma rays. Such independent detection method for the burnup factor allows a principally correct evaluation of the specific count rate of the irradiated monitor, which serves as a basic input for the determination of neutron field parameters.

Additional information

Authors: IRMM, ;JRC-GEEL (BE),
Bibliographic Reference: Article: Analytical Communications, 34 (1997), 133-135
Record Number: 199911149 / Last updated on: 1999-08-13
Original language: en
Available languages: en
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