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Treatment, Disposal, Re-Use of Building Demolition and Site Cleaning Wastes from Nuclear Facilities

Objective

The study concerns waste materials arising from building demolition and from site cleaning activities associated with decommissioning of nuclear facilities. The study does not consider wastes such as dismantled and/or disassembled process equipment, radioactive process inventories, etc.. as these wastes are assumed to have been removed from the facilities prior to building demolition and site cleaning.

The objectives are:

- Establish an overview of building demolition and site cleaning wastes arising from various types of fuel cycle facilities (enrichment, fuel manufacturing, power reactors, reprocessing, waste treatment, spent fuel encapsulation)
- Consider sampling, monitoring and analysis tools enabling the characterization and classification of these wastes
- Classify these wastes according to a 3 class scheme (release for unrestricted use, release for restricted use only, radioactive waste) and describe possible ways of reuse or disposal.
Information from FRG, UK and France is to be used. Three partners contribute to the study (NUKEM/D: enrichment, fuel fabrication, reactors, fuel encapsulation; SGN/F: reprocessing, waste treatment; WasteChem/UK: enrichment, fuel fabrication, reactors, reprocessing, waste treatment).
The study concerns waste materials arising from building demolition and from site cleaning activities associated with decommissioning of nuclear facilities.
The objectives of the study are to:
establish an overview of building demolition and site cleaning wastes arising from various types of fuel cycle facilities (enrichment, fuel manufacturing, power reactors, reprocessing, waste treatment, spent fuel encapsulation);
consider sampling, monitoring and analysis tools enabling the characterization and classification of these wastes;
classify these wastes according to a 3 class scheme (release for unrestricted use, release for restricted use only, radioactive waste) and describe possible ways of reuse or disposal.

According to the scope of the programme, the results from different countries and different facilities must be compiled in a unified scheme and parameters concerning the possible variations of radionuclide concentration limits and dose levels with corresponding uncertainties evaluated. The scheme produced forms a basis for comparisons. In this regard, a data bank was created and a computer programme development begun. For the data evaluation, at first, general premises and assumptions were necessary to establish which can be derived from the experiences of different decommissioning studies and on plant operational data.
Work programme:

The programme of the study is structured according to following tasks:

- Collection and compilation of waste data and characterization (3 partners)
- Investigation of sampling, monitoring and analysis tools (NUKEM)
- Material classification and investigation of re-use and disposal possibilities (3 partners)

For standardization purposes, the information obtained is to be re-arranged in such a way that it reflects the waste arisings from a 20 GWe fuel cycle scenario (equivalent to 600 metric tons of heavy metal per year).

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

Nukem GmbH
Address
Industriestraße 13
63755 Alzenau
Germany

Participants (2)

Société Générale pour les Techniques Nouvelles SA
France
Address
1 Rue Des Herons
78182 Saint-quentin-en-yvelines
WasteChem Ltd
United Kingdom
Address
Bramhall Centre Bramhall
SK7 2BY Stockport