首页> 外文会议>American Nuclear Society;International Nuclear Fuel Cycle Conference;Light Water Reactor Fuel Performance Conference >DEVELOPMENT OF SELF-HEALING COATING ON FUEL CLADDING FOR WATER-COOLING NUCLEAR REACTORS
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DEVELOPMENT OF SELF-HEALING COATING ON FUEL CLADDING FOR WATER-COOLING NUCLEAR REACTORS

机译:水冷核反应堆燃料熔覆自热涂层的研制

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A novel scheme for a bilayer coating with selfhealingability is proposed in this study. The candidatematerials for the coatings and the potential self-healingreaction are assessed in high-temperature aqueousenvironments and high-temperature air. The pure Cr_2O_3layer and the composite of Cr_2O_3 and MoO_3 are thecandidate materials for the outer layer and inner layer,respectively, due to their compatibility under normalcondition. Fe_2O_3-MoO_3 reactions exhibit a potentialability to heal the cracks because of a high reaction rateunder normal condition.
机译:具有自修复功能的双层涂层的新方案 在这项研究中提出了能力。候选人 涂料材料和潜在的自我修复 在高温水溶液中评估反应 环境和高温空气。纯Cr_2O_3 Cr_2O_3和MoO_3的复合层是 外层和内层的候选材料, 分别由于它们在正常情况下的兼容性 健康)状况。 Fe_2O_3-MoO_3反应显示出潜在的 由于高反应速率,具有修复裂缝的能力 在正常情况下。

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