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Bruet, M.; Michel, F.; Perdreau, R.
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Piles1977
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Piles1977
AbstractAbstract
[en] Three experimental methods of determining the fission power in a fuel pin, during irradiation in the SILOE Research Reactor, have been compared: the radial heat conduction is determinated by the measurement of the temperature gradient through fuel cladding, or by in-pile gamma scanning, or the incident neutron flux is monitored by self-powered detectors, and calculations of the fission rates are made by using the computer code APOLLO (a one-dimensional transport code). The methods are briefly described. The results are in agreement within 6%. This intercomparison is of interest due to the fact that, they would be used at different steps of the irradiation: previsionning, monitoring, post-irradiation examinations
[fr]
On a compare pour un barreau combustible, trois methodes pour determiner la puissance de fission lors de l'irradiation dans le reacteur experimental SILOE: la conduction radiale de la chaleur est determinee en mesurant le gradient de temperature dans la gaine, ou par gammametrie en pile, ou bien encore le flux des neutrons incidents est mesure par des collectrons et les taux de fission calcules a l'aide du code APOLLO (code de transport monodimensionnel). Les methodes sont brievement decrites. Les resultats sont en accord dans un domaine de 6%. Cette intercomparaison est interessante parce que ces methodes peuvent etre utilisees a differentes etapes de l'irradiation: prevision, monitorage, examen apres irradiationOriginal Title
Intercomparaison de determination de puissance dans un combustible irradie en pile: thermique, gammametrie, calculs neutroniques
Primary Subject
Source
22 Aug 1977; 17 p; 2. Symposium on reactor dosimetry: dosimetry methods for fuels, cladding and structural materials; Palo Alto, Calif., USA; 3 - 7 Oct 1977
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
A CODES, C CODES, COMPARATIVE EVALUATIONS, FISSION, FUEL CANS, FUEL PINS, GAMMA FUEL SCANNING, IN PILE LOOPS, MEASURING METHODS, NEUTRON DOSIMETRY, NEUTRON FLUX, PHYSICAL RADIATION EFFECTS, POWER DISTRIBUTION, REACTOR EXPERIMENTAL FACILITIE, SELF-POWERED DETECTORS, TEMPERATURE MEASUREMENT, THERMAL CONDUCTION
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