Preliminary Study on the Vitrification of Molten Salt Reactor Radwastes Containing Fluorides by Phosphate Glass

Qiao, Yanbo; Sun, Ya‐Ping; Liu, Xueyang; Qian, Zhenghua; Wang, Shuai; Ma, Hongjun

doi:10.1007/978-981-10-2314-9_57

Cited by 3 publications

(2 citation statements)

References 13 publications

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“…Several studies on incorporation of simulated fluoride waste from MSR were reported on phosphate glass, primarily due to lower melting temperature and relatively high solubility of halides 3 . Sodium aluminophosphate glass with waste loading 20 mol% (18.92 wt%) was reported by Sun et.al, 4,5 but crystallization occurs with a waste loading of 27.5 mol% (24.29 wt%). The addition of iron oxide in the phosphate glass matrix improved the chemical durability though reduced the waste loading significantly to 6.4 mol% (7.08 wt% waste including 2 wt% F) 4 .…”

Section: Introductionmentioning

confidence: 99%

Hot Isostatically Pressed (HIPed) fluorite glass‐ceramic wasteforms for fluoride molten salt wastes

et al. 2020

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Molten pyroprocessing salts can be used to dissolve used nuclear fuel from a reactor allowing recovery of the actinides. Previously, ANSTO have demonstrated hot isostatically pressed (HIPed) sodalite glass‐ceramic wasteforms for eutectic (Li,K)Cl salts containing fission products, but this system cannot be used for the analogous molten alkali fluoride salts (eg, FLiNaK), which have utility in the application of the next generation of nuclear reactors. In this work, a novel glass‐ceramic composite wasteform has been prepared by HIPing, as a candidate for the immobilization of fission product‐bearing FLiNaK salts. The wasteform has been tailored to immobilize the high fluoride content of the waste within fluorite, whereas the waste alkali elements are incorporated in a durable sodium aluminoborosilicate glass, with total waste loadings of ~17‐21 wt% achieved. It was also demonstrated that the speciation of Mo‐ and Sb‐simulated fission products was altered by adding Ti metal due to a controlled redox environment. The resulting candidate wasteform has been studied by X‐ray diffraction and scanning electron microscopy, including the HIP canister‐wasteform interaction zone, and its performance assessed via leaching studies using the PCT and ASTM C1220 leaching protocols. Dr Vance very much enjoyed the challenge of wasteform design for problematic nuclear wastes, for which fission product‐bearing FLiNaK salts are a clear example. His ability to hone in on a wasteform solution with viable waste loadings that meet performance requirements was testament to his nearly 40 years experience in nuclear waste immobilization. The samples discussed in this work represent the last wasteform materials that he prepared.

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Section: Introductionmentioning

confidence: 99%

Hot Isostatically Pressed (HIPed) fluorite glass‐ceramic wasteforms for fluoride molten salt wastes

et al. 2020

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“…The well-known works considering the Na 2 O-Al 2 O 3 -P 2 O 5 system and sodium-aluminium-phosphate glass as metastable phases formed upon cooling of the melt address important practical issues: investigation of the equilibrium crystallization of the melts on edges of the two-component cross sections and individual inner quasi-binary cross sections of the ternary system [3][4][5], determination of a vitreous region in the system [2,[6][7][8], studies of structure and properties of the glass [9][10][11][12][13][14][15][16][17][18][19], and selection of the glass composition for the immobilization of RW [2,8,[20][21][22][23][24][25][26][27][28][29][30]. However, only few works focus on the effect of the cooling regime of sodium-aluminum-phosphate melts on their crystallization and phase composition of the resulting products [31,32].…”

Section: Introductionmentioning

confidence: 99%

Subliquidus Phase Relations in the Low-Alumina Section of the Na2O–Al2O3–P2O5 System and the Radioactive Waste Vitrification

et al. 2018

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The formation of crystalline phases during cooling of the Na 2 O-Al 2 O 3 -P 2 O 5 melts obtained in corundum crucibles at a temperature of 1100°С and at atmospheric pressure from a pre-prepared glass with the composition close to that used for immobilization of highly active radioactive waste (RW) is studied. It is shown that under slow cooling, the crystallization process is accompanied by changes in the liquidus compositions of the melts leading to their transformations into glasses with compositions that, in some cases, are very different from the initial ones. A new topology of the melting diagram of a low-alumina section of three-component system is proposed, the melt's compositions are determined, and the temperatures of phase equilibria, which play a crucial role in industrial technologies, are estimated. The formation of crystalline phases under the slow cooling of the Na 2 O-Al 2 O 3 -P 2 O 5 melts should be taken into account in the vitrification of real RW.

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Phosphate-based glasses and glass ceramics for immobilization of lanthanides and actinides

Stefanovsky

Danilov

et al. 2019

Ceramics International

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Preliminary Study on the Vitrification of Molten Salt Reactor Radwastes Containing Fluorides by Phosphate Glass

Cited by 3 publications

References 13 publications

Hot Isostatically Pressed (HIPed) fluorite glass‐ceramic wasteforms for fluoride molten salt wastes

Hot Isostatically Pressed (HIPed) fluorite glass‐ceramic wasteforms for fluoride molten salt wastes

Subliquidus Phase Relations in the Low-Alumina Section of the Na2O–Al2O3–P2O5 System and the Radioactive Waste Vitrification

Phosphate-based glasses and glass ceramics for immobilization of lanthanides and actinides

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