Cement / Concrete in Nuclear Waste Management

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Cement / Concrete in Nuclear Waste Management 6 th FP IP ESDRED: LOW-pH CEMENT FOR A GEOLOGICAL REPOSITORY, 2005 Workshops on Mechanisms and Modelling of Waste/Cement Interactions Meiringen, 2005; Le Croisic, 2008; Ghent, 2013. International Symposium on Cement-Based Materials for Nuclear Wastes, Avignon 2011 NEA TDB Phase IV: Initiation Report Thermodynamic Data for Cement Minerals, 2012 State-of-the-Art Report

Collecting Ideas Responses by: AMPHOS21 (E), ARMINES (F), BGS (UK), BRGM (F), BTECH (FI), CEA (F), CIEMAT (E), CTM (E), KIT-INE (D), NRI-REZ (CZ), PSI (CH), SCK CEN (B), UNILOUGH (UK) Proposed Topics: Waste forms (containers, grouts): 21 Repository engineering (seals, support, backfill): 13 Geology (grouts, alkaline disturbed zone): 4 Possible approach Laboratory and Field scale experiments Analogues Process and system modelling

Reasons for a TSWG: SRA Key Topics 2 Waste forms and their behavior 2.2 Release from ILW and their detailed characterization 2012-2016, H Key Topic 3: Technical feasibility and long-term performance of repository components 3.10 Long-term behaviour of seals and plugs 2011-2017 H 3.11 Evolution of cement-based seals 2015-2023 M 3.12 Interaction of cement with clays 2016-2024 M 3.13 Optimisation of low ph cements 2016-2022 M

Issues of the TSWG Tentative list of issues for a TSWG: Remaining issues concerning basic understanding the stability of phase compositions under expected conditions Understanding the behaviour and potential reactions under unexpected/disturbed conditions ph and redox buffer capacity in various cementitious environments Radionuclide retention under highly alkaline conditions Proposed issues by NDA: Long-term evolution, interactions between barrier materials, and effects on cement properties. Long-term fate of radionuclides in cement based EBS Basic process understanding to be integrated into models for long-term predictions e.g.: 4 H 2 + Ca 2+ + SO 4 2- H 2 S + 2 H 2 O + Ca 2+ + 2 OH - (Truche 2009, low ph) Radionuclide retention / Long-term fate of RN

How to proceed? Discussion/information with WMOs (ANDRA, ONDRAF NIRAS, NDA, SKB) Exchange Forum is an adequate chance I don't see principle differences, rather general agreement Different degrees of details and mapping of topics TSWG could design a project by definition of topics/workpackages thematic mapping of topics according priorities, schedules, etc. estimation of time/resources required proposal of partners/contributors clarify organistion, etc. Meeting of interested groups?

NDA Long-term evolution, interactions between barrier materials, and effects on cement properties. Long-term Cement Studies (LCS) Grimsel URL Nearfield evolution of cement based systems long term NRVB performance as backfill and grout, leaching of aged cements Longevity of chemical conditioning Äspö ILW long term experiments, concept optimisation, engineering and design Vitrified ILW durability in cementitious environments Long-term fate of radionuclides in cement based EBS Chemical containment demonstration experiments, sorption, (co)precipitation etc Mechanisms of radionuclide uptake to cement based materials, longevity of radionuclide sorption (reversibility) Impact of cement additives and other EBS components on radionuclide mobility (long term, e.g. following cellulose degradation)

Ideas on Waste forms (containers, grouts) Impact of saline groundwater Changes in ph (high/low alkaline fluids etc) Influence on corrosion processes Carbonation by the breakdown of organic components in the waste Sulphatisation by deep ground waters Impact of magnesium (from MAGNOX). Impact of sulphatisation / carbonation of CSH/CASH on radionuclide adsorption and retardation. Gas generation Thermal impacts Ground-freezing (permafrost). Aging (inc. shrinkage) Changes in porosity of the system by formation of secondary solid phases Influence of the redox evolution due to scrap corrosion under hyperalkaline conditions Speciation of radionuclides under hyperalkaline conditions Formation of secondary alteration phases able to retain components of the waste Formation of secondary radionuclide solid phases under the hyperalkaline conditions with the development of different redox conditions in the presence of scrap materials. Variation of the diffusivity of radionuclides due to alteration of cement based matrices Generation of organic complexants Complexation of radionuclides by organics, either present or degraded from those in the waste forms, under high ph environments. Calcium as a competing metal for radionuclides towards the organic ligands Changes in strength, permeability etc

Ideas on Repository engineering (seals, support, backfill) Impact of saline groundwater Changes in ph (high/low alkaline fluids etc) Influence on corrosion Carbonation in response to back-reaction with bicarbonate in groundwater and carbon dioxide and bicarbonate generated by the breakdown of organic components in the waste Sulphatisation from reaction with sulphate-rich deep ground waters or from oxidation of sulphide minerals in the host rocks Impact of magnesium (from MAGNOX). Ground-freezing (permafrost). Sulphatisation /carbonation of CSH/CASH on radionuclide adsorption and retardation and potential re-release of radionuclides. Interfaces Cement/bentonite interactions Interactions and evolution of properties of low-alkali cements (ph<11) Metals/bentonite interactions Radionuclide sorption, formation of secondary solids.