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Hot Isostatically Pressed (HIPed) fluorite glass‐ceramic wasteforms for fluoride molten salt wastes
Journal of the American Ceramic Society ( IF 3.5 ) Pub Date : 2020-06-07 , DOI: 10.1111/jace.17293
Daniel J. Gregg 1 , Eric R. Vance 1 , Pranesh Dayal 1 , Rifat Farzana 1 , Zaynab Aly 1 , Rohan Holmes 1 , Gerry Triani 1
Affiliation  

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.

中文翻译:

热等静压(HIPed)萤石玻璃陶瓷废料,用于氟化物熔融盐废料

熔融热解盐可用于溶解来自反应堆的废核燃料,从而回收act系元素。以前,ANSTO演示过热等静压(HIPed)方钠石玻璃陶瓷废料,用于含有裂变产物的低共熔(Li,K)Cl盐,但是该系统不能用于类似的熔融碱式氟化物盐(例如,FLiNaK)。在下一代核反应堆的应用中具有实用性。在这项工作中,HIPing制备了一种新型的玻璃陶瓷复合废料,作为固定带有裂变产物的FLiNaK盐的候选物。废料的形状经过专门设计,可以将废料中的高氟化物含量固定在萤石中,而废碱元素则掺入耐用的铝硼硅酸钠玻璃中,废物总装载量约为17-21 wt%。还证明了由于受控的氧化还原环境,通过添加钛金属改变了钼和锑模拟裂变产物的形态。通过X射线衍射和扫描电子显微镜(包括HIP罐与废物的相互作用区域)研究了生成的候选废物形态,并通过使用PCT和ASTM C1220浸出方案的浸出研究评估了其性能。万斯博士非常喜欢针对有问题的核废料进行废物形式设计的挑战,对此,带有裂变产物的FLiNaK盐就是一个明显的例子。他在具有满足性能要求的可行废物装载量的废物形式解决方案中进行磨练的能力证明了他在核废物固定化方面近40年的经验。
更新日期:2020-08-10
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