Published October 2009
| Version v1
Miscellaneous
Fatigue Crack Growth Tests for Mod.9Cr-1Mo Steel at High Temperature Conditions
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Sungkyunkwan University, Suwon (Korea, Republic of)
Description
Mod.9Cr-1Mo steel (G91) is the currently favored structural material for several high temperature components of a Sodium-cooled Fast Reactor and it became a registered material for ASME Section III, Subsection NH in 2004. The creep-fatigue crack initiation and growth tests for a G91 tubular specimen including a machined defect have been performed by Kim. The fatigue crack growth tests a G91 compact tension (CT) specimen have been performed in this study
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
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027105
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKS; CREEP; FATIGUE; REACTOR MATERIALS; SODIUM COOLED REACTORS; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICAL PROPERTIES; REACTORS; TEMPERATURE RANGE
Optional Information
- Notes
- 5 refs, 4 figs, 2 tabs