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Abstract

The objective of this study is the calculation of dose induced by a radioactivity unit for workers and the public concerned by the concerete coming from dismantling. Then, the material radioactivity inducing a give dose can be calculated. This report gives the values for concrete. The radiological impact for all applications is calculated using realistic scenarios and exposure parameters. The first part of this report describes the management of gravel coming from buildings demolition. The second part concerns French waste management, specially in the case of nuclear installations dismantling. The third part explains the methodology used in the radiological impact study. The last part presents the results and proposes radioactivity thresholds for concrete. The appendixes contain: the description of practices in the matter of concrete crushing and building blocks manufacturing; the explanation of the parameter values of the radiological impact study; and a compilation of mass activity levels found in natural or manufactured products.

Additional information

Authors: HARISTOY D, CEA, CEN Fontenay-aux-Roses (FR);GUETAT P, CEA, CEN Fontenay-aux-Roses (FR);CHAPUIS A-M, CEA, CEN Fontenay-aux-Roses (FR)
Bibliographic Reference: EUR 16004 FR (1995) 168pp., FS, ECU 18.50
Availability: Available from the (2)
ISBN: ISBN 92-827-5286-0
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