Cesium immobilization in (Ba,Cr)-hollandites: Effects on structure

Tumurugoti, Priyatham; Sundaram, S. K.; Misture, Scott T.

doi:10.1016/j.jssc.2017.10.008

Cited by 12 publications

(22 citation statements)

References 30 publications

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“…Fission product 137 Cs is one of the most important artificial radionuclides generated from nuclear reactors, nuclear weapon tests, radioactive wastes, or waste liquid [20]. It is a gamma emitter with radiotoxicity, high volatility, mobility, and a relatively long half-life (close to 30 years) [47], which can be present in LLW, ILW, and HLW [48].…”

Section: Simulants Of 137 Cs and Experimental Methodsmentioning

confidence: 99%

“…In another study [20], which investigated the effects of Cs substitution on the crystal structure of phase-pure hollandite of the system, Ba 4 were used as starting materials for the preparation of the hollandite samples. Unlike Yang et al's study, the starting materials were dissolved individually in a suitable solvent and homogenized by mixing the solutions.…”

Section: Simulated 137 Cs In the Immobilization Methods By Usingmentioning

confidence: 99%

“…In Lian et al's study about the ion beam irradiation in La 2 Zr 2 O 7 -Ce 2 Zr 2 O 7 [46], Ce was used as an analog element for Pu because of the similarity with regard to the ionic size and oxidation state of Ce and Pu. In the experiment, CeO 2 , ZrO 2 and La 2 O 3 powders were mixed and sintered in air at "d" is the mean diagonal length of the tunnel cross section, and "R wp " is the weighted Rietveld parameter [20]. Decompose at high temperature, releasing Cs 2 O for the solid-phase reaction; CsOH is not used because it is strongly alkaline and will react violently with the metal container en, the prepared powders were reduced, treated, and sealed under vacuum containing residual He in quartz vials.…”

Section: Simulants Of 239 Pumentioning

confidence: 99%

“…e main purposes of these studies are summarized as developing new solidifying materials, increasing the loading of radioactive waste, reducing the leaching of radionuclides, enhancing the mechanical strength of solidified bodies, and reducing the disposal difficulty and cost. Additionally, computer simulation methods [13,[19][20][21][22][23], such as quantum mechanical and empirical models of atomic bonding, density functional theory plus Hubbard U correction (DFT + U), energy minimization, molecular dynamics (MD), and Monte Carlo (MD) methods, have also been widely applied to study the radiation effects in various solidified bodies.…”

Section: Introductionmentioning

confidence: 99%

“…e use of Cs 2 CO 3 or CsOH might adversely affect the research results and lead to lowconfidence research conclusions. (ii) Ceramic is considered to be an ideal host for HLW [44,45], and some researchers [14,20,23] used Cs 2 CO 3 or CsNO 3 to prepare Cs-containing ceramic waste forms by calcining the raw materials to over 1000°C. Differently, the preparation of Pu-(or Ce-) containing ceramic waste forms needs special treatment to reduce Pu(IV) (or Ce(IV)) to Pu(III) (or Ce(III)) [25,46].…”

Section: Introductionmentioning

confidence: 99%

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Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification

Wang

et al. 2020

Science and Technology of Nuclear Installations

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Although many types of simulated radionuclides have been widely used as a substitute for actual nuclear waste in the studies of nuclear waste solidification, the understanding of the applicability and validity of simulated radionuclides is still insufficient. In particular, the selection and use of simulated radionuclides, which can play a decisive role in the accuracy of the experimental results, still lack unified or integrated references. This paper provides a critical review on the selection, experimental methods, and applicability of the most commonly studied simulated radionuclides, followed by a careful discussion and recommendation of simulated radionuclides suitable for different solidified bodies. The main factors (e.g., temperature, pH, and atmosphere) affecting the choice of simulated radionuclides were analyzed in detail. This work helps to integrate the selection and use of simulated radionuclides, and it will be beneficial for improving the effectiveness of nuclide solidification research.

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Section: Simulants Of 137 Cs and Experimental Methodsmentioning

confidence: 99%

Section: Simulated 137 Cs In the Immobilization Methods By Usingmentioning

confidence: 99%

Section: Simulants Of 239 Pumentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification

Wang

et al. 2020

Science and Technology of Nuclear Installations

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Exploring the links between crystal chemistry, cesium retention, thermochemistry and chemical durability in single-phase (Ba,Cs)1.33(Fe,Ti)8O16 hollandite

et al. 2020

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Cs3Bi2I9-hydroxyapatite composite waste forms for cesium and iodine immobilization

et al. 2022

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Perovskite-based ceramic composites were developed as potential waste form materials for immobilizing cesium (Cs) and iodine (I) with high waste loadings and chemical durability. The perovskite Cs3Bi2I9 has high Cs (22 wt%) and I (58 wt%) content, and thus can be used as a potential host phase to immobilize these critical radionuclides. In this work, the perovskite Cs3Bi2I9 phase was synthesized by a cost effective solution-based approach, and was embedded into a highly durable hydroxyapatite matrix by spark plasma sintering to form dense ceramic composite waste forms. The chemical durabilities of the monolithic Cs3Bi2I9 and Cs3Bi2I9—hydroxyapatite composite pellets were investigated by static and semi-dynamic leaching tests, respectively. Cs and I are incongruently released from the matrix for both pure Cs3Bi2I9 and composite structures. The normalized Cs release rate is faster than that of I, which can be explained by the difference in the strengths between Cs-I and Bi-I bonds as well as the formation of insoluble micrometer-sized BiOI precipitates. The activation energies of elemental releases based on dissolution and diffusion-controlled mechanisms are determined with significantly higher energy barriers for dissolution from the composite versus that of the monolithic Cs3Bi2I9. The ceramic-based composite waste forms exhibit excellent chemical durabilities and waste loadings, commensurate with the state-of-the-art glass-bonded perovskite composites for I and Cs immobilization.

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Cesium immobilization in (Ba,Cr)-hollandites: Effects on structure

Cited by 12 publications

References 30 publications

Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification

Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification

Exploring the links between crystal chemistry, cesium retention, thermochemistry and chemical durability in single-phase (Ba,Cs)1.33(Fe,Ti)8O16 hollandite

Cs3Bi2I9-hydroxyapatite composite waste forms for cesium and iodine immobilization

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