The effect of boron on zeolite-4A immobilization of iodine waste forms with a novel preparation method

Liu, Yi; Wei, Guilin; Feng, Yaxin; Lu, Xirui; Yan, Chen; Sun, Runjie; Peng, Lin; Ma, Min; Zhang, Yu; Zhang, Zhentao

doi:10.1007/s10967-020-07079-8

Cited by 32 publications

(3 citation statements)

References 50 publications

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“…Iodosodalite [e.g., Na 8 (AlSiO 4 ) 6 I 2 ] is a highly durable wasteform attracting a significant amount of continued interest. In particular, recent developments include further details on the use of glass binders to enable densification at 750 °C (Chong et al, 2020(Chong et al, , 2018, the use of cold sintering to potentially eliminate the need to use glass binders (Hassan et al, 2020), the use of sol-gel methods (Kroll et al, 2020), the immobilization of AgI (Kuo et al, 2018;Maddrell, 2019), the interzeolite conversion to sodalite (Liu et al, 2021(Liu et al, , 2020An et al, 2020), and the direct conversion of waste streams into sodalite (Neeway et al, 2016;Bollinger et al, 2022).…”

Section: Sodalitementioning

confidence: 99%

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Review of recent developments in iodine wasteform production

et al. 2022

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Radioiodine capture and immobilization is not only important to consider during the operation of reactors (i.e., I-131), during nuclear accidents (i.e., I-131 and I-129) or nuclear fuel reprocessing (i.e., I-131 and I-129), but also during disposal of nuclear wastes (i.e., I-129). Most disposal plans for I-129-containing waste forms (including spent nuclear fuel) propose to store them in underground repositories. Here, iodine can be highly mobile and, given its radiotoxicity, needs to be carefully managed to minimize long-term environmental impacts arising from disposal. Typically, any process that has been used to capture iodine from reprocessing or in a reactor is not suitable for direct disposal, rather conversion into a wasteform for disposal is required. The objectives of these materials are to use either chemical immobilization or physical encapsulation to reduce the leaching of iodine by groundwaters. Some of the more recent ideas have been to design capture materials that better align with disposal concepts, making the industrial processing requirements easier. Research on iodine capture materials and wasteforms has been extensive. This review will act as both an update on the state of the research since the last time it was comprehensively summarized, and an evaluation of the industrial techniques required to create the proposed iodine wasteforms in terms of resulting material chemistry and applicability.

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Section: Sodalitementioning

confidence: 99%

“…The use of an additive can potentially aid the interzeolite transformation. Mixing NaI with Zeolite-4A (Si: Al = 1) in the presence of B 2 O 3 can yield sodalite after sintering at 750 °C (Liu et al, 2020). The B 2 O 3 promotes the formation of iodosodalite at a lower sintering temperature.…”

Section: Sodalitementioning

confidence: 99%

Review of recent developments in iodine wasteform production

et al. 2022

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“…The iodine is not easily released due to its chemical resistance to aqueous media with K sp = 8.52 × 10 −17 . However, the release of sliver is also regulated by the Resource Conservation and Recovery Act (40 CFR 261) so that AgI should be immobilized by a chemically stable matrix to satisfy the regulation [1][2][3][4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Effects of Bi2O3, Al2O3, PbO on silver tellurite glass for radioactive iodine immobilization

Kang

Lee

Choi

et al. 2020

J Radioanal Nucl Chem

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An iodine immobilization matrix, the AgI-Ag 2 O-TeO 2 glass system, was developed. The effects of different additives, i.e., Bi 2 O 3 , Al 2 O 3 , and PbO, on performance were investigated. In an ambient atmosphere and at 800 °C, the melting of the glass precursor mixture was completed after 1.0 h, without significant loss of the constituent elements of the glass except for aluminum. The loading of iodine in the matrix was approximately 11-15% by weigh, excluding oxygen. The normalized releases of all the elements from the matrix were below the order of 10 −1 g/m 2 , which satisfies US regulation (2 g/m 2 ). Additionally, each additive had a different effect on the glass system, and their effects on element release from the matrix were clarified.

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Immobilization of iodine waste in B2O3–Bi2O3–ZnO based materials: maximum solid solubility

Wei

Yang

et al. 2020

J Radioanal Nucl Chem

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The effect of boron on zeolite-4A immobilization of iodine waste forms with a novel preparation method

Cited by 32 publications

References 50 publications

Review of recent developments in iodine wasteform production

Review of recent developments in iodine wasteform production

Effects of Bi2O3, Al2O3, PbO on silver tellurite glass for radioactive iodine immobilization

Immobilization of iodine waste in B2O3–Bi2O3–ZnO based materials: maximum solid solubility

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