论文部分内容阅读
探讨了Zr-4管截面塑性(收缩系数CSR)测定的基本原理及试验方法,为全面研究核燃料包套材料的力学性能提供了重要依据.
The basic principle and test method of measuring the plasticity (shrinkage coefficient CSR) of Zr-4 tube were discussed, which provided an important basis for comprehensively studying the mechanical properties of the nuclear fuel cladding material.