Corrosion of carbon steel components in the French high-level waste programme: evolution of disposal concept and selection of materials

Crusset, Didier; Deydier, Valérie; Necib, Sophia; Gras, Jean-Marie; Combrade, P.; Féron, Damien; Burger, Emilien

doi:10.1080/1478422x.2017.1344416

Cited by 33 publications

(42 citation statements)

References 26 publications

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“…If licensed, CIGEO (Centre Industriel de stockage GEOologique) will be built nearby. [ 1 ] The HLW disposal concept has to meet various safety requirements at different stages of the disposal facility lifetime. Indeed, in addition to ensure that radioelements are fully confined for several centuries during the disposal, it has to satisfy a reversibility requirement, that is, a potential retrieving of the waste over the operation period of at least 100 years.…”

Section: Introductionmentioning

confidence: 99%

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Potential influence of microorganisms on the corrosion of carbon steel in the French high‐ and intermediate‐level long‐lived radioactive waste disposal context

Diler

Leblanc²,

Gueuné³

et al. 2020

Materials & Corrosion

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In the context of the high‐level radioactive waste disposal CIGEO, the corrosion rate due to microbially influenced corrosion (MIC) has to be evaluated. In France, it is envisaged to dispose of high‐ and intermediate‐level long‐lived radioactive waste at a depth of 500 m in a deep geological disposal, drilled in the Callovo‐Oxfordian claystone (Cox) formation. To do so, a carbon steel casing will be inserted inside disposal cells, which are horizontal tunnels drilled in the Cox. A specific cement grout will be injected between the carbon steel casing and the claystone. A study was conducted to evaluate the possibility of MIC on carbon steel in the foreseeable high radioactive waste disposal. The corrosiveness of various environments was investigated at 50°C and 80°C with or without microorganisms enriched from samples of Andra's underground research laboratory. The monitoring of corrosion during the experiments was ensured using gravimetric method and real‐time corrosion monitoring using sensors based on the measurements of the electrical resistance. The corrosion data were completed with microbiological analyses including cultural and molecular characterizations.

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Section: Introductionmentioning

confidence: 99%

“…The main objective of this filling material is to balance the transitory acidic conditions in the medium induced by the oxidation of the pyrite. [ 1,2 ] In addition, the alkalinity provided by the cement is expected to favor the steel passivity. [ 3–5 ]…”

Section: Introductionmentioning

confidence: 99%

Potential influence of microorganisms on the corrosion of carbon steel in the French high‐ and intermediate‐level long‐lived radioactive waste disposal context

Diler

Leblanc²,

Gueuné³

et al. 2020

Materials & Corrosion

Self Cite

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“…A micro-tunnel casing made from a different CS (API 5L X65 grade) with a wall thickness of 2.5 cm will be applied surrounding the CS overpack and emplaced in the drift (Fig. 2b) 12 . These waste packages will subsequently be embedded in filling materials (cement and bentonite mixture) with a wall thickness of about 10 cm, Fig.…”

Section: Introductionmentioning

confidence: 99%

“…The selection of CS as the overpack material was based on the consideration that CS tends to corrode uniformly under the conditions prevailing at this repository, so the corrosion rate is more predictable compared to the localized corrosion 13 . After deposition of the waste package, the repository environment will evolve from a hot and humid oxic environment to an anoxic environment re-saturated with groundwater at the geothermal temperature 12 . Similar to the U.S. program, each waste package contains a greater amount of encapsulant metal (1500 kg) than the nuclear waste glass within (400 kg) 14 .…”

Section: Introductionmentioning

confidence: 99%

Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

2020

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This review covers the corrosion interactions between different materials that are relevant to the disposal of high-level nuclear waste, in particular the waste forms and containers. The materials of interest are borosilicate glass, crystalline ceramics, metal alloys, and any corrosion products that might form. The available data show that these interactions depend on the structure, chemistry, thermodynamic history, and proximity of the materials in contact, as well as the environmental attributes, such as temperature, solution chemistry, and radiation. Several key mechanisms that govern these interactions are highlighted. Scientific gaps and open questions are summarized and discussed.

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“…After closure, CO 2 gas will be dissolved in the natural interstitial water after rehydration of the claystone. This dissolution will induce transitory acidic conditions (carbonic acid) which may influence the corrosion kinetics of the carbon steel components of the disposal cell [7,8]. Therefore, the understanding and extent of pyrite alteration should be assessed.…”

Section: Introductionmentioning

confidence: 99%

Experimental Study of Pyrite Oxidation at 100 °C: Implications for Deep Geological Radwaste Repository in Claystone

et al. 2019

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The oxidation of pyrite is one of the near field processes of the chemical evolution of clay rock planned to host a deep geological radioactive waste repository during operation. Indeed, this process can lead to transitory acidic conditions in the medium (i.e., production of sulphuric acid, carbonic acid) which may influence the corrosion kinetics of the carbon steel components of some disposal cells. In order to improve the geochemical modelling of the long-term disposal, the oxidation of pyrite in contact with clays and carbonates at 100 °C must be evaluated. In this study, special attention was paid to the pyrite oxidation rate thanks to an original experimental set-up, involving several pyrite/mineral mixtures and a reactor coupled to a micro gas chromatograph (PO2 and PCO2 monitoring). Although thermodynamic modelling expects that hematite is the most stable phase in a pure pyrite heated system (low pH), experiments show the formation of native sulfur as an intermediate product of the reaction. In the presence of calcite, the pH is neutralized and drives the lower reactivity of pyrite in the absence of native sulfur. The addition of clay phases or other detrital silicates from the claystone had no impact on pyrite oxidation rate. The discrepancies between experiments and thermodynamic modelling are explained by kinetic effects. Two laws were deduced at 100 °C. The first concerns a pure pyrite system, with the following law: r P y = 10 − 4.8 · P O 2 0.5 · t − 0.5 . The second concerns a pyrite/carbonates system: r P y + C a = 10 − 5.1 · P O 2 0.5 · t − 0.5 where PO2 corresponds to the partial pressure of O2 (in bar) and t is time in seconds. Different mechanisms are proposed to explain the evolution with time of the O2 consumption during pyrite oxidation: (i) decrease of the specific or reactive surface area after oxidation of fine grains of pyrite, (ii) decrease of O2 pressure, (iii) growing up of secondary minerals (Fe-oxides or anhydrite in the presence of calcium in the system) on the surface of pyrite limiting the access of O2 to the fresh surface of pyrite, and (iv) change in the pH of the solution.

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Corrosion of carbon steel components in the French high-level waste programme: evolution of disposal concept and selection of materials

Cited by 33 publications

References 26 publications

Potential influence of microorganisms on the corrosion of carbon steel in the French high‐ and intermediate‐level long‐lived radioactive waste disposal context

Potential influence of microorganisms on the corrosion of carbon steel in the French high‐ and intermediate‐level long‐lived radioactive waste disposal context

Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

Experimental Study of Pyrite Oxidation at 100 °C: Implications for Deep Geological Radwaste Repository in Claystone

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