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N ational approach and experience on disposal of ILW France

N ational approach and experience on disposal of ILW France. Vienna, 9 September 2013. National Waste and Radioactive Material Inventory (Andra 2012). Total volumes of wastes in 2010 (m 3 ). The French waste classification takes into account both activity level and half life.

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N ational approach and experience on disposal of ILW France

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  1. National approach and experience on disposal of ILWFrance Vienna, 9 September 2013

  2. National Waste and Radioactive Material Inventory (Andra 2012) Total volumes of wastes in 2010 (m3) The French waste classification takesintoaccountbothactivitylevel and half life. High level Intermediatelevel and long lived Lowlevel and long lived Intermediate/lowlevel and short lived Verylowlevel N/A Foreseentotal volumes of wastesin 2020 and 2030 (m3) DP/12-0162

  3. Today French low and intermediate level-short lived waste are being disposed of at the industrial scale in near surface “Centre de stockage de l’Aube” (CSA) • The 2006 wasteactprovidesfor disposalprojects for: • Lowlevel-long livedwaste • Intermediatelevel-long livedwaste and High levelwaste • Opened in: 1992 • Capacity: 1,000,000 m3 • Average annual volume: 12,000 m3

  4. Intermediateleveland long-livedwasteCigéo Project

  5. IL-LLW and HLW are planned to beco-disposed in the deepgeologicalrepositoryproject (Cigéo) • The 1991 WasteAct • Creation of « Andra » as a public independant body • 3 research areas for High Level Long-livedWaste: P/T; long termstorage; geologicdisposal • 1996: Licence application for 3 URLs (clay; granite) • 1998: Governmentdecision to licence the Meuse/Haute-Marne URL • 2001: Intermediate Clay report, first NEA peerreview… • 2005: Feasibility/safetyassessmentof safegeologicaldisposal in Meuse/Haute-Marne clay layer, reviewed 2005-2006 • The 2006 Programme Act: Reduce/avoid the burden on future generations • Reduce volume and harmfulness of wastes • Reference option for final wastethat can no longer be treated: geologicalrepositorywith respect to reversibility (100 y at least) • Continue research on P/T (CEA) and interim storage (Andra) on a complementary basis. • 2009: Safety, reversibility and design options, reviewed 2010 • 2010-2012: Launch of the design phase • 2013: Public debate 2015: Licence application Around 2016: Law definingreversibility conditions 2025: Operation 5

  6. Cigéo WasteInventory • By law only end waste can be disposed of (no recyclable material) • Cigeo is designed for the waste generated by existing nuclear facilities, under operation (50 years for PWR) or licensed • Reserves to manage the industrial uncertainties * dont verres issus du traitement des CU MOX aujourd’hui entreposés IL-LLW (MAVL) Vitrified HLW Clads, ends Solidified effluents Maintenance waste Activatedwaste and ITER

  7. Cigéo Project requirements • The results of 20 years of R&D since 1991 have made it possible to issue • detailed project technical requirements. • Postclosure Safety • Protect humans and the environment from radioactivity and toxicity of waste • Oppose groundwater flow • Limit the release of radionuclides and immobilizethemwhithinrepository • Delay and mitigate the migration of radionuclides • Preservation of the favorable properties of host clay • Nuclear safety and security in operation • Contain radioactive substances, protect people against exposure to ionizing radiation, control of nuclear criticality, remove the thermal power, vent gases • Failures and internal and external hazards risk management • Waste emplacement and retrievability • Receive, prepare and emplace waste packages • Close the repository • Allow retrieval of the waste packages • Control, monitor, observe • Sustainable development, corporate and social responsibility • Project governance

  8. Cigéo Project Surface Facilities Vent and Service Shafts Waste Transfer Ramp HLW RepositoryCells ILW RepositoryCells U/G Facility HLW Emplacement Waste Transfer ILW Emplacement 8

  9. IL-LLW Disposal Packages • Before emplacement, ILW will be grouped into precast concrete rectangular robust containers: Mechanical assembly cover-body Prototype Manufacturing 9

  10. ILW DisposalCells • ILW disposalcells are horizontal tunnels located at the median of the host clay layer: • Thickconcretelining to limit long termdeformations; • Ventilation of ILW repositorycells as long as they are not closed. ConcreteLining ILW Disposal Package Emplacement/retrievalprocesses and equipments are beeingdeveloped and prototyped: Trolley Stacker Technique PreStacking Technique 10

  11. Reversibility issues • The reversibility conditions shallbe set forth by a new Act. • The reversibility of the repositoryshouldbegranted, as a precaution, for at least 100 years (2006 Act). • Reversibilityshall not jeopardizesafety. • Based on an analysis of the various motivations for reversibility, Andra proposes an approachrelying on: • Technicalmeasures to enhance the retrievability of waste packages. • Stepwisedecision-making to control the disposalprocess. Retrieving the waste packge Transfer to surface Opening of the cell

  12. Cigéoproject: Time schedule 2011 2012 2013 2014 2015-2018 2019-2024 2025 2030 New Act on reversibility conditions Project requirements Public debate Preparation of license application Instruction of license application Preliminary and basic design Detailed design Phase 1 construction/tests CigéoPhase 1 operation URL Operation

  13. Lowleveland long-livedwaste

  14. Lowlevel and long-livedwaste • Graphite waste: 23,000t • 36Cl is the main contributor to the long-term radiological impact of disposed graphite waste • 14C (5,530 y) is the main long-lived radionuclide in graphite waste • 3H (12,3 a) is the main short-lived radionuclide • Radium bearing waste: 50,000t • Other (bituminous waste; Th/U/Ra contaminated objects; Disused RSS…)

  15. Examples of management options under study for graphite waste Graphite waste Direct packaging after dismantling Sorting • Partial decontamination of graphite waste allows either • Co-disposal of decontaminated graphite with Ra-bearing waste in near surface repository; • Complete destruction (gasification) of graphite • Concentrated residues can be disposed of with intermediate level - long lived waste (deep geological repository). Treatment radionuclides selective extraction Sleeves and others Piles Decontaminated graphite Packaging Extracted radionuclides 36Cl, 14C, 3H … Packaging Specific repository Cigeo (with ILW-LL) Shallow repository project Cigeo (with ILW-LL) Gasification Immobilisation and packaging Concentrated residues packaging Conditioning/ packaging Cigeo (with ILW-LL) Shallow repository Project

  16. … • The acceptability of graphite waste in a shallow repository depends in particular on: • the inventory of 36Cl and 14C (on the inventory of 241Am, 239Pu, 241Pu and on 94Nb as well as), • on the leaching rate of 36Cland on the fraction of organic 14C, • on site characteristics.

  17. Shallow disposal concept • The shallow disposal consists of a repository implementation within a low permeability clay formation at a depth of about 15 meters provided the host formation is outcropping. • Once completed, the pits are covered with a layer of compacted clay excavated from the site and stored prior to its reuse. • The waste isolation capability is available as long as the geodynamic site evolution does not significantly modify the repository configuration (i.e. via erosion). With regard to its depth and the expected geological conditions, the stability of the repository is estimated to be about 50,000 to 100,000 years.

  18. Shallow disposal concept • The repository is designed for long-lived waste containing: • Radionuclides with a low mobility and a radioactive period such that sufficiently low activities have been reached by decay in less than 50,000 years. The preservation of physical, chemical and hydraulic conditions limiting radionuclide mobility should be insured. The foreseen radionuclides are the ones with a period lower or equal to that of Carbon-14 (5,700 years). It covers in particular Radium-226 (1,600 years); • Restricted activity of Plutonium and Americium; • Restricted activity of radionuclides that do not decay sufficiently within 50,000 to 100,000 years such as Thorium-232 and Uranium-238 and Uranium-235; • Restricted activity of long-lived, potentially highly mobile radionuclides. • Waste acceptance criteria will be adapted to site performance. • Design of disposal pits will be adapted to waste characteristics. • Waste packaging to be defined in relation with repository design. • Site characteristics are needed to advance the repository design

  19. Next steps for LL-LLW • Geological survey was launched mid-2013 for the implementation of a shallow repository, along with dialogue with stakeholders. • Andra will issue a report in 2015 with proposals for an industrial strategy for the management of the different kinds of low level long lived wastes, particularly on the base of : • R&D results • Site investigations data • LL-LLW management scenarios conclusions

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