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Evaluation of thermal stability in deep geological repository and nuclear criticality safety of spent nuclear fuel vitrified in iron phosphate glass

机译:磷酸铁玻璃中玻璃化的乏核燃料在深部地质库中的热稳定性和核临界安全性的评估

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Iron phosphate glasses with low melting temperatures of similar to 1300 degrees C were developed to immobilize spent nuclear fuels (SNFs). The glasses have densities of similar to 3.15 g/cm(3) and glass transition temperatures of similar to 540 degrees C that are high enough to endure the temperatures in geological repositories. The waste loading of CeO2 in the glass was similar to 21.92 wt%, which corresponds to similar to 30.38 wt% of UO2 at the same molar ratio. Normalized elemental releases from the product consistency test were well below the regulated limit of 2 g/m(2). Effective neutron multiplication factor k(eff) was 0.755, which is below nuclear criticality safety regulation (k(eff) = 0.95). Vitrified SNF occupies one-eleventh of the repository space compared to direct disposal of the same amount of UO2, excluding left-over low-level wastes. (C) 2019 Elsevier Ltd. All rights reserved.
机译:已开发出具有类似于1300摄氏度的低熔点温度的磷酸铁玻璃,以固定乏核燃料(SNF)。玻璃的密度接近3.15 g / cm(3),玻璃化转变温度接近540摄氏度,足以承受地质库中的温度。在玻璃中,CeO2的废料负荷与21.92 wt%相似,在相同的摩尔比下,相当于30.38 wt%的UO2。产品一致性测试中的标准化元素释放量远低于2 g / m(2)的规定限值。有效中子倍增因子k(eff)为0.755,低于核临界安全性法规(k(eff)= 0.95)。与直接处理相同数量的UO2相比,玻璃化SNF占据了存储库空间的十一分之一,不包括剩余的低水平废物。 (C)2019 Elsevier Ltd.保留所有权利。

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