Preliminary Developments of Miniplate-Type Fuel of U-2.5Zr-7.5Nb Alloy Dispersed and Cladded in Zircaloy  

作　　者：Natalia Mattar Cantagalli Kelly Cristina Martins Faeda Rafael Witter Dias Pais Ana Maria Matildes dos Santos Wilmar Barbosa Ferraz 

机构地区：[1]CDTN/CNEN (Centro de Desenvolvimento da Tecnologia Nuclear), Belo Horizonte 31270-901, Brazil

出　　处：《Journal of Energy and Power Engineering》2014年第8期1409-1414,共6页能源与动力工程（美国大卫英文）

摘　　要：Nuclear fuel based on uranium metal alloys is utilized in research and test reactors. For the purpose of the reduction of fuel enrichment, high densities of uranium-235 in this kind of fuel are needed. This can be achieved when uranium alloys are used containing elements such as Zr, Mo and Nb. The construction of fuel element with high-uranium density requires materials with low cross sections for neutron absorption, stability under irradiation and absence of the chemical interactions between the fuel and cladding elements. In case of U-Zr-Nb alloys, Zry （zircaloy） cladding is a better option due to the fact that they have a higher chemical compatibility when compared with the use of aluminum alloys. This study aims to develop plate type nuclear fuel using the U-2.5Zr-7.5Nb alloy dispersed in Zry. Powders of this uranium based alloy and Zry were obtained by hydriding-dehydriding process. These powders were homogenized, compacted in pellet that was sandwiched in plates and frame of Zry. This assembly was hot rolled forming the dispersion fuel miniplate.

关 键 词：Nuclear fuel plate U-Zr-Nb alloy Zry 

分 类 号：TG146.414[一般工业技术—材料科学与工程] TL2[金属学及工艺—金属材料]