Abstract: In the development roadmap of magnetic confinement fusion energy of China, a fusion engineering test reactor named China Fusion Engineering Test Reactor (CFETR) was proposed. CFETR aims to bridge the gap between International Thermonuclear Experimental Reactor (ITER) and demonstration reactor (DEMO). One of the main goals of CFETR is to achieve tritium fuel self-sustaining, with tritium breeding ratio exceeding 1.0. In order to achieve tritium fuel self-sustaining and safe tritium disposal, it is very important to establish a closed tritium fuel cycle. Therefore, a tritium plant composed of various tritium treatment systems is a necessary condition for the successful operation of CFETR. According to the overall group planning, in the CFETR engineering design stage, it is necessary to give the detailed engineering conceptual design and engineering feasibility verification of CFETR tritium plant system. In the middle of the ‘Thirteenth Five-Year Plan’, due to the engineering design requirements of tritium plant of CFETR, three major key technical research projects related to tritium plant were deployed in the ‘National Research Project on the Development of Magnetic Confinement Nuclear Fusion Energy’. Tritium plant mainly consists of three loops: the inner cycling loop, the outer cycling loop and the confinement and safety loop. The main task of the outer cycling loop of tritium plant is to realize tritium breeding in the breeder blanket, and extract and separate the breeding tritium for continuous tritium supply. The outer cycling loop consists of several units, including tritium production by breeder, tritium extraction, hydrogen isotope separation and tritium measurement, which are interrelated and indispensable. Relying on the national key research and development plan ‘Tritium Extraction and Measurement Engineering Technology for CFETR Breeding Blanket’, new progress was made in the research of several tritium breeding technologies. It mainly includes the following aspects. An in-pile tritium production and in-situ tritium extraction demonstration experiment with a total activity level of approximately one hundred curies has been done on CMRR. The 1∶1 scale demonstration experimental of tritium extraction and hydrogen isotope separation in breeding blanket has been carried out with dynamic extraction efficiency of 99.1%, shutdown extraction efficiency of 99.95%, hydrogen isotope separation concentration multiple of 104 times and recovery efficiency of 99.26%. A pilot experiment of tritium-containing water treatment based on water distillation has been carried out, with dilution exceeding 2 000 times and concentration exceeding 20 times. Based on this, the design and construction of tritium plant of fusion reactor in the future are prospected.