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Abstract

For intermediate storage, transport and final disposal of radioactive waste, the waste package has to fulfill the waste acceptance criteria defined by the nuclear regulatory institutions of the various countries. Important especially for transport, storage or final disposal is the radiochemical content of the waste package. The fulfilment of the waste assay criteria concerning radiochemical content can be verified by the execution of a quality assurance programme from the waste production up to the waste package, ready for final disposal, complemented by computations and/or measurements at the beginning, during and at the end of the waste treatment. A programme to develop measurement systems, instruments and analysis methods is executed in order to make an experimental assay of waste packages possible with sufficient accuracy. Different assay methods for the determination of fissile and non-fissile radionuclide containment in waste are discussed.

Additional information

Authors: BONDAR L, JRC Ispra (IT);DIERCKX R, JRC Ispra (IT);NONNEMAN S, JRC Ispra (IT);PEDERSEN B, JRC Ispra (IT);SCHILLEBEECKX P, JRC Ispra (IT)
Bibliographic Reference: Paper presented: 6th Environmental Quality and Waste Management Conference, Denver (US), April 18-20, 1995
Availability: Available from (1) as Paper EN 38949 ORA
Record Number: 199510683 / Last updated on: 1995-07-07
Category: PUBLICATION
Original language: en
Available languages: en
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