Advances in Materials Science for Environmental and Nuclear Technology
Advances in Materials Science for Environmental and Nuclear Technology
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环境与核技术材料科学进展
DOI：
10.1002/9780470930991.ch1
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发表时间：
2010
期刊：
影响因子：
--
通讯作者：
Davoisne C
中科院分区：
文献类型：
--
作者：
Davoisne C
了解放射性损害的影响和钚处置的潜在陶瓷宿主中惰性气体的容纳能力，对于确定地质处置期间的长期行为十分重要。用2 MeV的Kr+离子对锆英石和Nd掺杂锆英石的多晶样品进行了非原位辐照，以模拟α衰变过程中发生的钚核反冲。采用聚焦离子束（FIB）制备的薄片，通过透射电子显微镜（TEM）研究了辐照引起的微观结构和化学变化。在这项研究中，从原始和辐照陶瓷FIB的TEM切片制备的可行性进行了论证。在Kr+辐照后，观察到样品在表面处是无定形的，并且鉴定了样品的原始部分和辐照部分之间的界面。未观察到显著的化学修饰。
Understanding the effect of radiation damage and noble gas accommodation in potential ceramic hosts for plutonium disposition is important for determining long-term behaviour during geological disposal. Polycrystalline samples of zirconolite and Nd-doped zirconolite were irradiated ex-situ with 2 MeV Kr+ ions to simulate plutonium nuclei recoil which occurs during alpha decay. The microstructural and chemical modifications induced by the irradiation were investigated by Transmission Electron Microscopy (TEM) on thin sections prepared by Focused Ion Beam (FIB). During this study, the feasibility of TEM section preparation from pristine and irradiated ceramics by FIB was demonstrated. After Kr+ irradiation, the samples were observed to be amorphous at the surface and an interface between the pristine and irradiated parts of the specimen was identified. No significant chemical modification was observed.