Published 2000 | Version v1
Miscellaneous

Effect of Chloride ion and Zirconium hydride on thr corrosion and SCC behaviors of functionally graded Zirconium alloy p.683

  • 1. Department of Metallurgical and Materials Engineering, Sunmoon University, Asam (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Effect of chloride ion and zirconium hydride on the corrosion and stress corrosion cracking behaviors of functionally graded zirconium alloy was studied to develop an advanced nuclear cladding tubing. The functionally graded zirconium alloy had composition gradient of niobium, which was prepared with a hot pressing followed by cold deformation. The corrosion rates and potentials decreased with increasing FeCl3 and hydride content. The corrosion potentials before and after hydriding are -4.3 VSHE, 8.8x10-5 Acm-2 and -12.5 VSHE, 3.9x10-4 Acm-2, respectively. The stress corrosion cracking susceptibility decreased with elongation rate, indicating the saturation value at 5x10-7 sec-1. SEM observation showed that brittle fracture with corrosion products and pits were observed on the failed surface of hydrided zirconium alloy, suggesting anodic dissolution occurred during exposure after cracking growth along zirconium hydrides. (author)

Part of:
Proceedings of the Symposium on Nuclear Materials and Fuel 2000

Additional details

Publishing Information

Publisher
Korea Atomic Energy Research Institute
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of Symposium on Nuclear Materials and Fuel 2000
Imprint Pagination
1167 p.
Journal Page Range
p. 683-690

Conference

Title
Symposium on Nuclear Materials and Fuel 2000
Dates
24-25 Aug 2000
Place
Taejon (Korea, Republic of)

Optional Information

Notes
15 refs., 2 tabs., 5 figs.; This record replaces 31057965