Development and application of low-pH concretes for structural purposes in geological repository systems

Alonso, C.; Calvo, José Luis García; Hidalgo, Antonio Vásquez; Luco, Luis Fernández

doi:10.1533/9781845699789.3.286

Cited by 15 publications

(12 citation statements)

References 58 publications

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“…At body temperature, the hydration reactions may be written as in Equations ( 6) and (7) The calcium aluminate cements also create a high pH environment and release calcium ions, 106 which are prerequisites for bioactivity, albeit these cements are not as alkaline as the calcium silicate cements. 107 Some investigators have combined the calcium aluminate cements or silica with calcium silicate cements [108][109][110] for use in dentistry. Presumably, the goal is to combine silicate ion release for osteogenesis and the benefits of the calcium aluminate cement for acid resistance.…”

Section: Methodsmentioning

confidence: 99%

Calcium silicate and calcium aluminate cements for dentistry reviewed

et al. 2021

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Calcium silicate cements were identified as excellent materials for dentistry, particularly for dental procedures contacting the dental pulp or root system. Both calcium silicate and calcium aluminate cements cause the biomineralization (precipitation of hydroxyapatite [HA] phenomena and shield dental tissues from the underlying cement (a foreign body material). The cements also elute ions to stimulate cytokines that contribute to the healing of the dental pulp or in the tissue surrounding the root of a tooth. The cements serve as a foundation for other dental restorative materials. This paper reviews the cement phases, properties, in vivo reactions, and clinical benefits from the use of calcium silicate and calcium aluminate ceramic cements.

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Section: Methodsmentioning

confidence: 99%

Calcium silicate and calcium aluminate cements for dentistry reviewed

et al. 2021

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“…On the other hand, in the case of radioactive waste disposal facilities for which the evaluation of extremely longterm stability is required, it has been shown that high alkaline components leached from cementitious materials can cause dissolution of minerals in the nearby bentonite and changes in the pore structure of the rock (Gaboreau et al 2011), and therefore proper evaluation of leaching behavior is important. A site selection process for geological repositories for spent fuel, such as highlevel waste (HLW), long-lived intermediate-level waste (L/ILW), and low-level radioactive waste (LLW) is underway all over the world (Alonso et al 2010;Akiyama et al 2011;Savage 2018;etc.). The safety of the HLW, L/ILW, and LLW repositories shall be ensured by a multi-barrier concept and distancing from living area.…”

Section: Introductionmentioning

confidence: 99%

Cement and Concrete for Nuclear Waste Management

Nakarai¹,

Kosakowski²

2022

ACT

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The safe management and disposal of radioactive wastes are of critical importance for maintaining a sustainable society. In nuclear waste management, cement and concrete are commonly used to immobilize radioactive waste. Cementation is a common technique used for conditioning low-level and intermediate-level radioactive wastes, which should ensure safe interim storage of waste packages, and act as a first long-term barrier during waste disposal. In addition, cement-based materials are utilized for construction and barrier materials in surface disposals for very low-level to low-level waste and deep geological disposals for low-level, intermediate-level, and high-level wastes.Furthermore, recovery from the nuclear disaster at the Fukushima Daiichi Nuclear Power Station (F1NPS) is an important and urgent issue in Japan. To solve the difficult problems associated with radioactive contaminated materials in the plant and in the environment, contributions of cement and concrete technologies are highly expected.The understanding end prediction of the long-term evolution of cement materials interacting with wastes and other barrier materials during interim and final storage is indispensable and needs to be studied by experts from different scientific and engineering disciplines. The very long times associated with the safe disposal of radioactive waste, which are well beyond the lifetime of ordinal engineered structures and therefore not experimentally accessible, make this task even more demanding.In the first part of this special issue, three technical contributions summarize research and development projects for nuclear waste management with cement and concrete technologies in Japan. and Ichikawa and Hamamoto (19-1275) give general overviews on the use of cement-based materials for low-level radioactive waste (LLW) and for high-level radioactive waste (HLW), respectively. Furthermore, Abe and Iida (20-236) present a comparative discussion of approaches used for LLW in Japan and Belgium.In the second part, the contributions concentrate on processes and applications related to the performance assessment of cement and concrete for nuclear waste management. The scientific papers describe sorption experiments with Cl, I, HTO, and C by Nedyalkova et al. (19-811), diffusion experiments with NaCl of leached cement paste by Kurmisawa et al. (19-426), leaching experiments of cement paste with quick setting admixture by Yokozeki et al. (19-1173), immersion experiments of cement-bentonite samples by Nakarai et al. (19-433, 19-447), and chemo-mechanical modelling of degraded concrete by Oda et al. (19-1075).Finally, the third part contains contributions that investigate, in a broad sense, how cement and concrete technologies can be used to deal with the aftermath of the F1NPS nuclear disaster. At first, a technical paper by summarizes the outcome of a research initiative that aimed at identifying the cause and extent of radioactive contamination of concrete at the F1NPS.A set of scientific contributions is related to water abso...

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“…On the other hand, in the case of radioactive waste disposal facilities for which the evaluation of extremely longterm stability is required, it has been shown that high alkaline components leached from cementitious materials can cause dissolution of minerals in the nearby bentonite and changes in the pore structure of the rock (Gaboreau et al 2011), and therefore proper evaluation of leaching behavior is important. A site selection process for geological repositories for spent fuel, such as highlevel waste (HLW), long-lived intermediate-level waste (L/ILW), and low-level radioactive waste (LLW) is underway all over the world (Alonso et al 2010;Akiyama et al 2011;Berner et al 2013;Savage 2018;etc.). The safety of the HLW, L/ILW, and LLW repositories shall be ensured by a multi-barrier concept and distancing from living area.…”

Section: Introductionmentioning

confidence: 99%