Abstract: The UO2+Zr alloy fuel assembly is the most widely used nuclear fuel system for the current light water nuclear reactor. However, the Fukushima Daiichi nuclear disaster revealed the primary safety risks of UO2+Zr alloy fuel system under accident, thereby various international programs have been launched to develop accident tolerant fuel (ATF). ATF is a new generation of fuel system developed to enhance the ability of nuclear fuel assembly under severe accident. The primary domain research of accident tolerant fuel is to design and improve current nuclear fuel forms and develop enhanced thermal conductivity UO2 nuclear fuel on the basis of little change in industry. At present, the candidate fuel systems for thermal conductivity enhanced UO2 that have achieved progress are the UO2-SiC, UO2-BeO, UO2-diamond and UO2-Mo. For the UO2-SiC and UO2-diamond systems, the details of the interfacial reactions between SiC/diamond and UO2 have been poorly understood. The role of the evolution of properties for SiC and diamond on the thermos-physical performance of UO2 under irradiation has yet to be fully defined. Nevertheless, electric field assisted sintering (FAST) technology is an effective method to suppress the interfacial reaction and fabricate UO2-SiC and UO2-diamond. In the UO2-BeO system, the excellent chemical compatibility between BeO and UO2, and the enhancement effect for thermal conductivity of UO2 has been demonstrated through the extensive work. Accordingly, UO2-BeO is regarded as the candidate fuel system for industrial application. However, the Be presenting as the scarcity material for the strategic resource, and the toxic nature of BeO as well as the transformation of spent fuel reprocessing processes, should be considered for industrialization. In the UO2-Mo system, Mo has been considered as the most potential additive among the metals, and indicates outstanding thermal conductivity enhancement for the three-dimensional network distribution. Moreover, such microstructure is beneficial for retaining fission products. Compared with other additives, Mo has the property of higher neutron absorption cross section, and thus the amount of addition should be reasonably regulated. While such fuel system also should be investigated in detail. It is well accepted that the candidate fuel system above is still lacks of irradiation data for assessments. High-throughput preparation and machine learning could be introduced into the development of thermal conductivity enhanced UO2 to accomplish the industrial application at an earlier time. This review offers a retrospection of the research efforts with respect to the thermal conductivity enhanced UO2, and provides the fabrication process, microstructure and thermal conductivity respectively. Then the current problems confronting the thermal conductivity enhanced UO2 are concerned as well as the application prospects are presented to the benefit for ATF in light water reactor.
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2019, Vol. 33 
