Categorization of Cement Hydrates by Radionuclide Sorption Mechanism

Noshita, Kenji; Nishi, Takashi; Yoshida, Takuma; Fujihara, Hiromasa; Saito, Noriyuki; Tanaka, Satoru

doi:10.1557/proc-663-115

Cited by 13 publications

(5 citation statements)

References 9 publications

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“…The ‘0D’ in the sample notation represents 0 days leaching. The trace for the blank cement sample without waste simulants (sample B) shows the formation of calcium silicate hydrate (C–S–H), portlandite (CH), hydrotalcite (Hc) and monosulphoaluminate (AFm) as expected from the literature 1,3,4,8 in addition to the gehlenite (G) contained in the original BFS.…”

Section: Resultssupporting

confidence: 53%

“…The results show that the introduction of CsNO 3 and/or Sr(NO) 3 have different impacts on the cement phases formed in the system. X-ray diffraction and SEM indicates that the majority of the CsNO 3 was not associated with any other phases.…”

Section: Incorporation Of Cs and Srmentioning

confidence: 96%

“…It has been reported that both Cs and Sr interact with calcium silicate hydrate (C-S-H) gel. 2 The Cs in OPC cements appears to be mainly sorbed onto the C-S-H gel or to remain in the pore solution, [2][3][4] whereas Sr is thought to be retained in only the C-S-H gel, [5][6][7] with the Sr 2z ions substituting for the Ca 2z ions.…”

Section: Introductionmentioning

confidence: 99%

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Leaching behaviour of cementitious nuclear wasteforms containing caesium and strontium

Gashier¹,

Miura²,

Hashimoto³

et al. 2014

Advances in Applied Ceramics

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The leaching behaviour and physicochemical properties of cementitious nuclear wasteforms containing caesium and strontium waste simulants has been investigated. The cement wasteform consisted of a 9∶1 blend of blast furnace slag and ordinary Portland cement. Both non-loaded samples and samples that were waste loaded with 3 wt-% caesium and strontium added as nitrates have been studied. The cement hydration phases in the samples were identified, and the porosity and microstructure were analysed before leaching. The samples were leached for up to 6 months and the leached elements quantified. In the waste loaded cements, portlandite was not formed, and the monosulphate AFm phase appeared to be altered by the incorporation of the Sr(NO3)2. Incorporation of Cs and Sr also resulted in the increase in the leach rate of Ca2+.

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Section: Resultssupporting

confidence: 53%

Section: Incorporation Of Cs and Srmentioning

confidence: 96%

See 1 more Smart Citation

Leaching behaviour of cementitious nuclear wasteforms containing caesium and strontium

Gashier¹,

Miura²,

Hashimoto³

et al. 2014

Advances in Applied Ceramics

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“…1. The results regarding the adsorption behavior of Cs on C-S-H with varying C/S ratios are consistent with the results reported by Noshita et al (2000) and Ochs et al (2006). Conversely, the C/S ratio of C-S-H was found to have nearly no effect on the adsorption of Sr on C-S-H, which suggests a difference between the adsorption behaviors of Sr and Cs on C-S-H.…”

Section: Modeling Of Interaction Of C-s-h With Cs and Sr Ionssupporting

confidence: 90%

“…The adsorption amount of Cs, which like Na and K is a monovalent cation, increases in the same manner as that of Na and K when the C/S ratio decreases (Faucon et al 1997;. The coexistence of Na and K has also been reported to affect the adsorption behavior of Cs because of the competitive adsorption among them (Noshita et al 2000;Viallis et al 1999;Viallis-Terrisse 2000;Viallis-Terrisse et al 2001). Conversely, with regard to divalent Sr, it has been reported that the solid-to-liquid ratio and the C/S ratio of C-S-H as well as the Ca and Sr concentrations in the aqueous phase affect the adsorption of Sr on C-S-H (Tits et al 2004(Tits et al , 2006Wieland et al 2008;.…”

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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General Understanding of Calcium Silicate Hydrates

Baltakys,

Dambrauskas

2024

Synthetic Gyrolite

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Categorization of Cement Hydrates by Radionuclide Sorption Mechanism

Cited by 13 publications

References 9 publications

Leaching behaviour of cementitious nuclear wasteforms containing caesium and strontium

Leaching behaviour of cementitious nuclear wasteforms containing caesium and strontium

Cement and Concrete for Nuclear Waste Management

General Understanding of Calcium Silicate Hydrates

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