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Reduced Enrichment for Research and Test Reactors
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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting


A. Delfinand R. Mazón

ININ, Mexico


In the framework of the Technical Cooperation Regional Project for Latin America RLA/4/018 for the biennium 2001-2002, one of the  activities identified is the characterization of spent fuel. Of these activities an important one is not doubt the physical condition of spent fuel because an appropriate identification of the fuel status will prevent problems of fuel leaks, corrosion problems etc.

As part of the activities of the project was decided that countries no having visual inspection and sipping systems should be very desirable to have them as a result of this project. The Triga reactor of Mexico does not have both of them, therefore, it was decided the need of having both system.

The paper describe first the way we designed and constructed a remote Visual Inspection System and example of how is operated. Along the experience and problems we have had with the system. Also we will present the design of the Sipping system were two option were considered. First to take a sample of water after a convenient period of time passing through a circuit to a multichannel analyzer and to identify leakage by way of measuring Caesium-137. Second, exists the possibility that the Stainless Steel sleeve of the fuel has only very small failures, so it is going to be very difficult to have leakages unless the fuel is hot. Therefore we are evaluating the possibility of using heaters to increase the temperature of the fuel and succeed on detecting leakages. The results - we hope - will be ready to be presented at the meeting.

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Mr. Ruperto Mazon Ramirez

Nuclear Technology Manager
Instituto Nacional de Investigaciones Nucleares
Apdo. Postal 18-1027
C.P. 11801, D.F. Mexico
Phone: (52 55) 5329 7249
Fax: (52 55) 5329 7371
E-mail: [email protected]

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Last modified on July 29, 2008 11:34 +0200