Abstract: A tritium breeding blanket is a compulsory element for a demonstration power reactor (DEMO) in order to realize tritium breeding selfsufficiency. To verify the key technology, China participates in the ITER TBM project with the concept of Helium Cooled Ceramic Breeder Test Blanket Module (HCCB TBM). HCCB TBM is now completely in the preliminary design stage, and the material preparation technology and material data are the basis for supporting structural design, safety analysis and service condition evaluation. In this case, the research status of structural material low activation ferrite/martensitic (RAFM) steels, tritium breeder and neutron multiplier for HCCB TBM was summarized, and the research directions of these materials for the next phase were proposed. Through the recent main research literature and scientific and technological report, the composition design, manufacturing process, integrity of performance data, mechanical performance results and service performance evaluation of structural material low activated ferrite/martensite steel for HCCB TBM, functional material tritium breeder lithium orthosilicate and neutron multiplier beryllium were analyzed. The three materials developed in China preliminarily met the design requirements in terms of the rationality of the composition design, the industrialization degree and reliability of the manufacturing process, and the integrity of the performance required by the design. Both structural materials and functional materials will face the severe service conditions in the fusion experimental reactor, which require high performance of materials. A large number of existing data were the results of separate testing and analysis by various research projects, and its data reliability and systematism need to be further studied. In terms of structural materials, it is necessary to build performance data, test results and database based on a large number of traceable and standardized tests. In terms of functional materials, the research on the properties of tritium breeder pebble bed is insufficient and needs to be further improved, including thermomechanical properties, antiirradiation properties, tritium release properties, etc. Experimental studies are not carried out on the packing properties, thermomechanical properties and thermophysical properties of beryllium pebble bed at high temperature. These contents should be gradually carried out and continuously improved in the next step of material engineering certification and material comprehensive performance test, so as to provide technical support for the R&D and manufacturing of helium cooled ceramic breeder test blanket system in China. At the same time, based on reliable and a large number of production and test data, the material performance standards and databases of RAFM steel materials, tritium breeder materials and neutron multiplier materials for fusion reactor design can be established to support the design and research of fusion reactor in the future.