The reporter learned from the Institute of Metals, Chinese Academy of Sciences that prototype prototypes of major national science and technology projects and "special project of dragon boat-CNSC spent fuel transport container" developed by National Nuclear Science and Technology Commission recently passed the acceptance test. As an important part of domestication of key materials for spent fuel transport containers, The developed boron carbide enhanced aluminum (B4C / Al) neutron absorber material provides important support for the full localization of the container.
In recent years, B4C / Al neutron absorbing materials have been widely used in high density storage and transportation of nuclear fuel / spent fuel instead of traditional boron stainless steel and other neutron absorbing materials abroad. Due to the late commercialization of nuclear power, the development of neutron absorbing materials lags behind , B4C / Al neutron absorption material has long been dependent on imports, seriously restricting the development strategy of our country's nuclear power independence and going out.
In recent years, the Chinese Academy of Sciences Ma Zongyi Metallurgy Group and China Nuclear Power Engineering Co., Ltd. cooperation in the preparation of B4C / Al neutron absorber material, simulation service performance evaluation and full-size engineering research and development aspects of the project to tackle the large size blank In the process of ingot preparation, the interface control problem was solved, which broke through the high efficiency and high yield rolling forming bottleneck of high content B4C / Al sheet, developed welding tools and welding technology suitable for composite material welding, Full chain technology approach for the engineering application of the material laid a solid foundation has been developed B4C content of 15-35wt% of the series neutron absorber plate, and completed the accelerated corrosion, high temperature aging, accelerated irradiation and uniform boron Sexual test (neutron absorption method) and other experimental assessment, material performance fully achieved (such as corrosion resistance, etc.) was significantly better than similar foreign products.
At the same time, the metal for the first global high temperature gas-cooled reactor for new fuel components transportation, storage containers for neutron absorber material cylindrical structure needs of the first time in the country neutron absorption material of the coil plate operation and friction stir welding achieved Sub-absorbent material from the plate structure to the cylindrical structure of the breakthrough.Currently Huaneng Shandong Shidao Bay Nuclear Power Station HTR nuclear power plant demonstration project of new fuel components transportation, storage container has formally entered the mass production stage, the metal to undertake the container Neutron absorber plate supply mission.
Spent fuel, also known as irradiated nuclear fuel, is a type of nuclear fuel that has been exposed to radiation and used, usually from nuclear reactors in nuclear power plants.
