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Qualification of a Radioactive High Aluminum Glass for Processing in the Defense Waste Processing Facility at the Savannah River Site - 8410

机译:萨凡纳河站点国防废物处理设施中用于处理的放射性高铝玻璃的资格-8410

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At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a borosilicate glass for approximately eleven years. Currently the DWPF is immobilizing HLW sludge in Sludge Batch 4 (SB4). Each sludge batch is nominally two million liters of HLW and produces nominally five hundred stainless steel canisters 0.6 meters in diameter and 3 meters tall filled with the borosilicate glass. In SB4 and earlier sludge batches, the Al concentration has always been rather low, (less than 9.5 weight percent based on total dried solids). It is expected that in the future the Al concentrations will increase due to the changing composition of the HLW. Higher Al concentrations could introduce problems because of its known effect on the viscosity of glass melts and increase the possibility of the precipitation of nepheline in the final glass and decrease its durability. In 2006 Savannah River National Laboratory (SRNL) used DWPF processes to immobilize a radioactive HLW slurry containing 14 weight percent Al to ensure that this waste is viable for future DWPF processing. This paper presents results of the characterization of the high Al glass prepared in that demonstration.At SRNL, a sample of the processed high Al HLW slurry was mixed with an appropriate glass frit as performed in the DWPF to make a waste glass containing nominally 30% waste oxides. The glass was prepared by melting the frit and waste remotely at 1150°C. The glass was then characterized by1. determining the chemical composition of the glass including the concentrations of several actinide and U-235 fission products,2. calculating the oxide waste loading of the glass based on the chemical composition and comparing it to that of the target3. determining if the glass composition met the DWPF processing constraints such as glass melt viscosity and liquidus temperature along with a waste form affecting constraint that prevents the precipitation of nepheline (NaAlSiO_4) crystals in the glass melt4. measuring the durability of the glass using the ASTM Standard Product Consistency Test (PCT) leach test to determine if the durability of the glass based on B, Li, and Na releases met the requirements for acceptance in a US geologic repository5. measuring the leachability of several radionuclides using the ASTM Standard PCT leach test and comparing them to the B, Li, and Na releases6. examining the glass by scanning electron microscopy and energy dispersive X-ray spectrometry to determine if any crystals had formed in the glass melt.Results indicate that the high Al glass met all the requirements for processing and product quality in the DWPF.
机译:在萨凡纳河站点(SRS),国防废物处理设施(DWPF)一直将SRS的放射性高放废物(HLW)污泥固定在硼硅酸盐玻璃中已有约11年的历史。目前,DWPF正在将HLW污泥固定在第4批污泥(SB4)中。每批污泥标称是200万公升的高放废物,并标称生产500个直径为0.6米,高3米的装有硼硅酸盐玻璃的不锈钢罐。在SB4和更早的污泥批次中,Al的浓度一直很低(基于总干燥固体,少于9.5重量%)。可以预见,由于高放废物成分的变化,铝的浓度将在未来增加。较高的Al浓度可能会带来问题,因为它对玻璃熔体的粘度产生已知影响,并增加了最终玻璃中霞石沉淀的可能性,并降低了其耐久性。 2006年,萨凡纳河国家实验室(SRNL)使用DWPF工艺固定了含14%重量百分比的Al的放射性HLW浆料,以确保该废物可用于未来的DWPF处理。本文介绍了该演示中制备的高铝玻璃的表征结果。 在SRNL中,将经过处理的高Al HLW浆料样品与DWPF中执行的适当玻璃料混合,制成标称含量为30%的废氧化物的废玻璃。通过在1150℃下远距离熔化玻璃料和废物来制备玻璃。然后通过以下方式对玻璃进行表征: 1.确定玻璃的化学组成,包括几种act系元素和U-235裂变产物的浓度, 2.根据化学成分计算玻璃的氧化物废物负荷,并将其与目标物质进行比较 3.确定玻璃成分是否满足DWPF工艺约束条件(例如玻璃熔体粘度和液相线温度)以及废物形态影响约束条件,以防止霞石(NaAlSiO_4)晶体在玻璃熔体中沉淀 4.使用ASTM标准产品一致性测试(PCT)浸出测试测量玻璃的耐用性,以确定基于B,Li和Na释放量的玻璃的耐用性是否满足美国地质资料库接受的要求 5.使用ASTM标准PCT浸出测试测量几种放射性核素的浸出能力,并将其与B,Li和Na释放量进行比较 6.通过扫描电子显微镜和能量色散X射线光谱法检查玻璃,以确定在玻璃熔体中是否形成了任何晶体。 结果表明,高铝玻璃满足了DWPF中所有工艺和产品质量的要求。

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