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Conference Papers Year : 2015

Methodology to prepare the tritiated waste management : Defining WAC for an interim storage facility

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Abstract

Considering the high mobility of tritium through the package in which it is contained, the new 50-year storage concepts proposed by the CEA currently provide a solution adapted to the management of waste with high tritium concentrations. The 50-year intermediate storage corresponds to 4 tritium radioactive periods i.e. a tritium reduction by a factor 16.The waste acceptance criteria (WAC) for this interim storage concept will take into account the criteria applicable at Andra disposal centers, the reference scheme for the management of tritiated waste in France, and the safety of the facility. This will lead to define a set of waste specifications that describe the generic criteria such as acceptable waste forms, general principles and specific issues, e.g. conditioning, radioactive content, tritium content, waste tracking system, and quality control. This approach is a way to check in advance, during the design phase, how the future waste could be integrated into the overall waste management routes and identify possible key points that need further investigations (design changes, selection of materials, etc.). It supports the nuclear operator to ensure the compliance of the future waste packages with the disposal acceptance criteria.This paper details how the work done by the CEA has led to a storage facility project that not only takes into account the specificity of tritium, but also the producers' needs and Andra's disposal requirements. This will lead to define a set of waste specifications that describe the generic criteria such as acceptable waste forms, general principles and specific issues, e.g. conditioning, radioactive content, tritium content, waste tracking system, and quality control. This approach is also a way to check in advance, during the design phase of the waste treatment chain, how the future waste could be integrated into the overall waste management routes and identify possible key points that need further investigations (design changes, selection of materials, etc.): the results obtained are shown. It supports the nuclear operator to ensure the compliance of the future waste packages with the disposal acceptance criteria.
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Dates and versions

cea-02509676 , version 1 (17-03-2020)

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  • HAL Id : cea-02509676 , version 1

Cite

C. Decanis, D. Canas, F. Derasse, J. Pamela. Methodology to prepare the tritiated waste management : Defining WAC for an interim storage facility. 337ISFNT-12 - 12th International Symposium on Fusion Nuclear Technology, Sep 2015, Jeju Island, South Korea. ⟨cea-02509676⟩

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