Examination and Testing of an Active Glass Sample Produced by Cogema
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EXAMINATION AND TESTING OF AN ACTIVE GLASS SAMPLE PRODUCED BY COGEMA P. CHERON - Ph. CHEVALIER - R. DO QUANG - G. TANGUY M. SOURROUILLE - S. WOIGNIER*, M. SENOO - T. BANBA - K. KURAMOTO - T. YAMAGUCHI - K. SHIMIZU**, C. FILLET - N. JACQUET-FRANCILLON - J. GODARD - J.L. DUSSOSSOY F. PACAUD - J.G. CHARBONNEL* **, * COGEMA 2 rue Paul Dautier, 78140 V6lizy-Villacoublay, France JAERI, Tokai Research Establishment, Department of Environmental Safety ** Research, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan CEA-DCC-DRDD, CEN Valrho, 30200 Bagnols sur C~ze, France. *** ABSTRACT This paper presents the results of analyses and measurements performed on an active glass sample taken from the French vitrification facility R7. INTRODUCTION With the start-up of modem facilities UP3 and UP2-800 at La Hague, Cogema is operating a unique industrial complex able to service nearly eighty Light Water Reactors. The philosophy of commercial reprocessing is to separate recyclable materials (uranium and plutonium) on the one hand and to condition ultimate waste. In this context most of the activity in the waste is conditioned in borosilicate glass, by the vitrification process studied from over 25 years in France and successively implemented in the facilities AVM at Marcoule, R7 and T7 at La Hague, and in the Windscale Vitrification Plant at Sellafield (UK). The quality of the glass produced at La Hague is based on:
"* long-lasting
formulation and characterization studies [1, 2, 3] performed by the CEA, which resulted in specifications issued by Cogema, and approved by the French authority and confirmed by foreign customers and their authorities ; "* a comprehensive Quality Assurance and Quality Control (QA/QC) system, which conforms the ISO 9002 standard. An active sample of vitrified residue was exceptionally taken during routine production in the R7 facility in 1992. The resulting specimens were shared for examination and analyses between two independent laboratories operated by JAERI and the CEA. The aim of this study was to compare them with the data provided by the glass producer Cogema based on HLW analysis and process data and to check if they meet the specification, and thus to confirm the validity of the QA/QC system. SAMPLING The sample was taken from a normal glass batch, the theoretical mass of which is 200 kg. The sampling device used was placed inside a container, in the axis of a glass pour. After a cooling procedure, the graphite crucible was extracted and the sample removed.
Mat. Res. Soc. Symp. Proc. Vol. 353 0 1995 Materials Research Society
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The sample obtained was monolithic, unfractured and perfectly formed (weight : 400 g). It looked homogeneous without any separated phase such as yellow phase. The sample was then split between the two laboratories. CHEMICAL AND RADIOCHEMICAL ANALYSIS After complete dissolution in a hot cell the nuclear glass was analyzed by ICP-AES for the major constituents, and by a and y spectrometry and P counting for the radionuclides. Dissolution methods were developed by the CEA
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