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Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel; Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie

Conference:

Abstract

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.
Authors:
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
CEA-CONF-11816; CONF-9310279-
Reference Number:
SCA: 220600; 420500; PA: AIX-26:002046; EDB-95:007590; SN: 94001290145
Resource Relation:
Conference: Three days on gamma and x-rays spectrometry,Journees de spectrometrie Gamma et X 93,Saint-Remy-les-Chevreuse (France),12-14 Oct 1993; Other Information: PBD: 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; FUEL PELLETS; DIMENSIONS; SILOE REACTOR; GAMMA SPECTROSCOPY; COLLIMATORS; MANGANESE 54; P CODES; ZIRCONIUM 95; 220600; 420500; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; MATERIALS TESTING
OSTI ID:
10102994
Research Organizations:
CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Reacteurs Experimentaux
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Other: ON: DE95608459; TRN: FR9402825002046
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
6 p.
Announcement Date:
Jun 30, 2005

Conference:

Citation Formats

Gleizes, B. Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel; Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie. France: N. p., 1993. Web.
Gleizes, B. Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel; Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie. France.
Gleizes, B. 1993. "Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel; Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie." France.
@misc{etde_10102994,
title = {Application of Gamma spectrometry for dimensional measurement, by non destructive control, of irradiated nuclear fuel; Application de la spectrometrie gamma a la mesure dimensionnelle par controle non destructif sur combustible nucleaire irradie}
author = {Gleizes, B}
abstractNote = {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.}
place = {France}
year = {1993}
month = {Dec}
}