Abstract: The invention belongs to the technical field of nuclear reactor materials design, and discloses a method for improving the withstanding capability of the cladding material in the fast neutron irradiation environment, comprising the following steps: selecting the cladding material with the annular structure and placing it on the outer side of the metallic fuel slug, with leaving a 0.2-0.8 mm gap between the metallic fuel slug and the cladding material; processing the operation in a reactor subsequently, with an annealing process of the fast neutron reactor fuel during the operation of the reactor; improves the withstanding capability of the cladding material in the fast neutron irradiation environment.

Abstract: The invention relates to a field of nuclear reactor fuel temperature measurement and discloses a method of measuring nuclear reactor fuel temperature, comprising: S1: collect fission gas produced by nuclear reactors through a gas collection device, S2: measure pressure value and temperature value of the fission gas through pressure and temperature sensors, S3: obtain the corresponding fuel temperature by calculating the pressure value and temperature value, and the invention provides a method of measuring nuclear reactor fuel temperature, and it collects the fission gas discharged by fuels through a fission gas collection device, utilizes the sensitive relevance in a specific temperature range between the release amount of metal fuel fission gas and fuel temperature changes, and makes the pressure of metal fuel fission gas correspond to fuel temperature, thus to convert fuel temperature measurement which is difficult to achieve into fission gas pressure measurement which is easy to achieve.

Abstract: The disclosure discloses a high-burnup fast reactor metal fuel, wherein the reactor core is loaded with metal fuel made of natural uranium alloy U-50Zr. The metal fuel manually controls the temperature to realize phase transition, increase burnup, and extend the service life of fuel; increases the fuel burnup to increase uranium utilization and reduce the pressure of disposing nuclear waste; extends the fuel life cycle to reduce nuclear power costs and improve the economy of nuclear energy; effectively carries out the timely release of fission gas and the periodic elimination of fuel defects, thus reducing the fuel-cladding mechanical interaction caused by swelling, and increasing the safety.