Properties of phosphate glass waste forms containing fluorides from a molten salt reactor

Sun, Ya‐Ping; Xia, Xiaobin; Qiao, Yanbo; Zhao, Zhongqi; Ma, Hongjun; Liu, Xueyang; Qian, Zhenghua

doi:10.1007/s41365-016-0059-9

Cited by 8 publications

(10 citation statements)

References 24 publications

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“…The conceptual wasteform design was a GC whereby CaF 2 crystallized within a durable glass matrix, and this has largely been demonstrated. The benefit of the GC design is to produce a durable wasteform with fluoride loadings of around 7‐9 wt%, which is significantly higher than those produced by comparative glass wasteforms 4 . Simulated fission products were also included in the composition and their incorporation mechanism and speciation into the wasteform design has been a key aspect of this study.…”

Section: Resultsmentioning

confidence: 99%

“…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 . An iron phosphate glass was adopted to capture CsCl and SrF 2 , and the hydration resistant Fe–O–P bonds in the glass provided high chemical durability and ease of fabrication, although the majority of the halides were released during melting 6 .…”

Section: Introductionmentioning

confidence: 91%

“…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%

“…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 An iron phosphate glass was adopted to capture CsCl and SrF 2 , and the hydration resistant Fe-O-P bonds in the glass provided high chemical durability and ease of fabrication, although the majority of the halides were released during melting. 6 In this regard, an iron phosphate glass which consisted of Fe 2 O 3 -P 2 O 5 -B 2 O 3, and incorporating SrF 2 and CeF 3 as surrogate waste with 10 wt% waste loading, was produced without crystallization.…”

Section: Introductionmentioning

confidence: 99%

“…The waste loading and, in particular, the fluoride incorporation is higher than previously achieved waste loadings in reported literature. 4 The resulting wasteform was studied by X-ray diffraction and scanning electron microscopy, including the HIP canister-wasteform interaction zone, and its performance assessed via leaching studies using standard leaching protocols.…”

Section: Introductionmentioning

confidence: 99%

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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: Resultsmentioning

confidence: 99%