A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

Applications of carbide ceramics in nuclear reactors

“…以典型MAX相材料 Ti 3 AlC 2 为例, 它具有优异的高温抗氧化性能, 并且在 耐腐蚀和抗辐照方面都表现良好 [66] . 此外, 它比锆合金 材料的硬度大得多(图4(d)), 由于其独特的层状结构, MAX相材料具有低摩擦系数和良好的自润滑性, 可以 在没有润滑剂的情况下通过高速切削工具加工成各种 形状 [67] , 有望成为新一代核能系统中燃料的包壳材 料 [68] . MAX相材料与其他碳化物陶瓷材料的最大区别是 具有高温自愈合能力(图4(e), (f)).…”

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

“…One route is to develop alternative materials, such as SiC f /SiC composites [6,10,[52][53][54][55][56], FeCrAl stainless steels [57][58][59][60][61], Mo alloys [45,[62][63][64][65], and MAX phases (the family of layered ternary compunds (M n+1 AX n ) in which M is an early transition metal, A is an A-group element and X is either carbon or nitrogen.) [51,56,[66][67][68], which can completely replace zirconium alloys. The other route is to prepare coatings on the surface of the existing zirconium alloy claddings [13,33,34,[69][70][71][72][73][74].…”

“…Among the materials, new alternative cladding materials have several potential advantages that are helpful for improving the accident resistance of fuel cladding. For example, SiC f /SiC composites have excellent high-temperature mechanical properties, chemical properties, and neutron economy [10,31,46,56]. The FeCrAl alloy has an excellent corrosion/oxidation resistance and a relatively superior high-temperature strength under normal and accident conditions [10,31,46,56].…”

“…Mo, or Mo alloys, features an ultra-high melting point (2623 • C), excellent high-temperature strength, and high-temperature creep behavior [10,31,45]. MAX phases have a strong stiffness, good thermal conductivity, and high resistance to chemical attacks, and high-temperature oxidation [51,56,[66][67][68]. However, these new materials also have some specialproblems, such as the corrosion/dissolution of SiC that occurs under normal operating conditions of water-cooled reactors [10,46], the high tritium permeability of FeCrAl [10,46], and the high volatility of Mo under high-temperature oxidation conditions [10,45].…”

Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings

“…Nowadays, two main ATF strategies are considered. The first is to replace current cladding material with SiC f /SiC composites [13][14][15][16], FeCrAl , molybdenum alloys [20,[22][23][24][25] or Ni-based stainless steels [26]. Taking into account the duration and possible total costs for developing a new type of cladding material, this way is considered as a long-term strategy.…”