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Abstract

This work is undertaken in the framework of an assessment of the doses liable to be received by non-nuclear workers during the recycling of materials recovered from dismantled nuclear facilities. The present survey is focused on copper and aluminium, deriving mainly from electric cables. It consequently seemed advisable also to consider recovery of the cable insulating materials, mainly polyvinyl chloride (PVC). Estimated quantities are relatively low as compared with the steel quantities from the same source. A special case is also included: dismantling of the low and medium uranium enrichment plants at Pierrelate (France), where all pipework is made of an aluminium-magnesium alloy, AG3. Exposure scenarios with a non-negligible probability of occurrence are derived from these data. Probable values for doses received under the envisaged conditions are calculated. Initial waste activity levels are then defined so that internationally recommended reference levels will be respected. The mean specific activity of the main beta-gamma emitters in copper, aluminium and PVC are of the same order of magnitude, 10 Bq/g. For alpha emitters, specific activity levels depend on the material and the radionuclide concerned, ranging from 2 Bq/g to 10 Bq/g for copper and from 10 Bq/g to 50 Bq/g for aluminium.

Additional information

Authors: GARBAY H, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR);CHAPUIS A M, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR);CAHUZAC O, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR);GUETAT P, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR);HARISTOY D, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR);RENAUD P, CEA, Institut de Protection et de Sûreté Nucléaire, Fontenay-aux-Roses (FR)
Bibliographic Reference: EUR 13160 EN (1992) 136 pp., FS, ECU 15
Availability: (2)
ISBN: ISBN 92-826-3982-7
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