The reporter learned from the Institute of Metals of the Chinese Academy of Sciences that a prototype of the National Science and Technology Major Project and CNNC's special scientific and technological project “Dragon Boat-CNSC Spent Fuel Transport Container Development†project has passed the inspection and acceptance. As an important part of localization of key materials for spent fuel transportation containers, the boron carbide-reinforced aluminum (B4C/Al) neutron absorbing material developed by the metal has provided important support for the overall localization of containers.
In recent years, B4C/Al neutron absorbing materials have replaced traditional neutron absorbing materials such as boron stainless steel, which are widely used in nuclear fuel/spent fuel high density storage and transportation. Due to the late commercialization of nuclear power in China, research and development of neutron absorbing materials lags behind. B4C/Al neutron absorbing materials rely on imports for a long time, which seriously restricts China's nuclear power autonomy and development strategy of going global.
In recent years, the Ma Zongyi Research Group of the Institute of Metals of the Chinese Academy of Sciences cooperated with China Nuclear Power Engineering Co., Ltd. to conduct research on the B4C/Al neutron absorbing material preparation, simulated environmental service performance assessment, and the development of full-size engineering parts. Overcoming the problems of interfacial control during the preparation of large-size billets, breaking the bottleneck of high-productivity, high-yield-rate roll forming of high-content B4C/Al sheets, developing welding tools and welding processes suitable for welding composite materials, and opening up materials from materials. The development of a full-chain technology approach to device formation has laid a solid foundation for the engineering application of this material. A series of neutron absorbing plates with a B4C content of 15 to 35 wt% have been developed, and experimental evaluations such as accelerated corrosion, high temperature aging, accelerated irradiation, and boron uniformity test (neutron absorption method) have been completed. (such as corrosion resistance, etc.) is obviously better than similar foreign products.
At the same time, for the first time in the world, the need for a neutron-absorbing material cylindrical structure for transporting and storing containers of new high-temperature gas-cooled reactors for high-temperature gas-cooled reactors has been achieved. Coiled operation and friction stir welding of neutron-absorbing materials have been realized for the first time in China. Sub-absorbent material breaks from a plate-like structure to a cylindrical structure. At present, Huaneng Shandong Shidao Bay Nuclear Power Plant High-Temperature Gas-Cooled Reactor Nuclear Power Plant Demonstration Project The new fuel element transport and storage containers have officially entered the mass production phase, and Metals has undertaken the task of supplying all neutron absorption plates for the vessel.
Spent fuel, also known as irradiated nuclear fuel, is nuclear fuel that has been exposed to radiation and used, and is usually produced by nuclear reactors in nuclear power plants. (Reporter Hao Xiaoming)
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