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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:放射性高铝玻璃的资格,用于在萨凡纳河网站防御废物处理设施中加工 - 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 by 1. 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 target 3. 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 melt 4. 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 repository 5. measuring the leachability of several radionuclides using the ASTM Standard PCT leach test and comparing them to the B, Li, and Na releases 6. 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)已被固定SRS的放射性高放废物(HLW)污泥转化为硼硅玻璃大约11年。目前DWPF被固定在污泥批次4(SB4)HLW污泥。每个污泥批次名义上2000000升HLW的并产生名义上500不锈钢罐0.6米直径和3米多高填充有硼硅酸盐玻璃。在SB4和更早污泥批次,Al浓度一直是相当低的,(小于9.5重量%,基于总干固体)。据预计,在未来的铝浓度将因增加对高放废物的改变组成。高浓度的铝可能会带来问题,因为玻璃熔体的粘度其已知的效果,增加霞石的最终玻璃降水的可能性,并降低其耐用性。 2006年,萨凡纳河国家实验室(SRNL)用于DWPF处理以固定含14%重量的铝,以确保这些废物是可行的未来DWPF处理放射性高放射性废料浆。本文介绍了高Al玻璃的表征结果在演示准备。在SRNL,处理后的高Al HLW浆料的样品用如在DWPF进行使含有标称30%的浪费氧化物的废玻璃的适当的玻璃料混合。玻璃被通过熔化玻璃料制备并在1150℃下进行远程浪费。然后将玻璃的特点是1.确定所述玻璃包括几个锕系和U-235的裂变产物,2。基于所述化学成分的玻璃的氧化物废料加载并将其与那个的浓度的化学组成目标3.确定所述玻璃组合物满足了DWPF处理约束,诸如玻璃熔体粘度和液相线温度与影响约束防止霞石的沉淀(NaAlSiO_4)结晶在玻璃熔体4测量玻璃的耐久性的废物形式沿使用ASTM标准产品一致性试验(PCT)浸出试验,以确定是否基于B,Li和钠释放玻璃的耐久性在美国地质储存库5.符合验收要求测量几个放射性核素的使用ASTM可浸出标准PCT浸出试验,并将它们进行比较的B,锂,和Na释放6.通过扫描电子显微镜和电子检查玻璃NERGY色散X射线光谱法,以确定是否任何结晶在玻璃熔体形成了。结果表明,高铝玻璃满足所有的加工和产品质量在DWPF的要求。

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