Published October 2008 | Version v1
Miscellaneous

Water Loop System Development for IASCC tests at High Temperature

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

Description

The effect of a irradiation on a stress corrosion cracking (SCC) at a high temperature is needed for an application of new materials to a pressurized water reactor. Proton irradiation technique as an alternative tool of a neutron irradiation seems to appeal to evaluate the effect on the SCC behavior of stainless steels. The SCC technique can be used for a screening of various material and environmental conditions. However, the proton-irradiation should be confirmed for its role of in-core irradiation on crack growth and in performing a final verification of the effect of alternative irradiation on candidate alloys. In spite of the handicap of the proton irradiation, some test plans have been set up by using the proton irradiated materials due to a good feature of the technique such as a low radioactivity. This paper aims to introduce the SCC test facility for IASCC on the proton-irradiated materials

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2008 autumn meeting of the KNS
Dates
30-31 Oct 2008
Place
Pyongchang (Korea, Republic of)

Optional Information

Notes
1 ref, 2 figs