Published 1993 | Version v1
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Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel

Description

Gamma spectrometry is an efficient tool for measurement of radionuclides activity, but it can be used in a more qualitative way to determine the diameter of gamma radioactive materials. This application has been developed in CENG at Siloe research reactor, particularly for the determination of nuclear fuel swelling when irradiated during normal or incidental conditions. Gamma spectrometry takes place on the measurement of the sample activity profile at the main energy of a fission product, this fission product is chosen for its good cohesion with the fuel. The profile is compared to a simulation on the basis of a calculation in straight line attenuation of gamma radiation; the adjustment of the sample diameter in the calculation is made in order to obtain an agreement between measured and computed profiles. Several parameters can disturb the measurement (gamma emitters distribution in fuel section, radiation scattering...) and make the adjustment of a simulation pattern more difficult. Then it becomes necessary to qualify the method with an irradiated sample calibrated in diameter. (author). 6 figs., 5 refs

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Original title (French)
Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie

Publishing Information

Imprint Pagination
6 p.
Report number
CEA-CONF--11816

Conference

Title
Days ''Gamma and X spectrometry 93''.
Original Conference Title
Journees de spectrometrie Gamma et X 93
Dates
11-14 Oct 1993.
Place
Saint-Remy-les-Chevreuse (France).