Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 2002.05a
- /
- Pages.216.2-216
- /
- 2002
Corrosion behaviors with the variation of the accumulated annealing parameters in New Zr-allowy for the Nuclear Fuel claddings
핵연료 피복관용 Zr 신합금의 열처리변수에 다른 부식거동
Abstract
Keywords