Published 2000 | Version v1
Miscellaneous

Comparison of Zr-2.5Nb pressure tube fracture toughness and CCL using small-CT and large burst specimen

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

By using non-irradiated materials (quad- and double-melted) which had the same composition as irradiated materials of Zr-2.5Nb pressure tube (O-08, M-11) from the first domestic CANDU power reactor, Wolsung I the comparison analysis was carried out on the result derived from experiment of fracture toughness of the large and small specimen. The result showed that non-irradiated CCL had a tendency of decrease with temperature, while CCL of O-08 irradiated large sample maintained constant at room temperature and 250 deg. C. CCL of O-18 irradiated small sample showed higher tendency than that of M-11. Especially, in O-18 irradiated materials small specimen at room temperature had a tendency of more conservative than larger specimen. But at 250 deg. C the relative conservativeness in smaller specimen disappeared. (Hong, J. S.)

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. 848-856

Conference

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

Optional Information

Notes
9 refs., 9 figs.; This record replaces 31058068