Irradiation Effect on Mechanical Properties of C/C Composite Spring Coil of C/C Composite Control Rod for High Temperature Gas Cooled Reactors

抄録

C/C composite spring coil is expected to be fuel spacer and shock eliminator of C/C composite control rod for high temperature gas cooled reactors. To testify mechanical properties of C/C composite spring coil element after irradiation, high temperature irradiation test of neutron fluence up to 7.66×10²⁰cm² at 850°C was carried out and deformation behavior and fatigue strength of these irradiated spring coils were observed under cyclic loading. This paper presents design concept of C/C composite control rod and its elements, and summarized material data obtained.