High Temperature Fatigue Crack Growth Tests for Mod.9Cr-1Mo Compact Tension Specimen at 20 Hz Loading Frequency
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Sungkyunkwan University, Suwon (Korea, Republic of)
Description
Mod.9Cr-1Mo steel (G91) is currently the 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. It was chosen as a candidate material as IHTS piping and heat exchangers for a KALIMER-600. While ASME Subsection NH provides some material properties of Mod.9Cr-1Mo steel for a design purpose at high temperature conditions, there is lack of material properties such as fatigue crack growth and creep crack growth especially for robust structural integrity evaluations. The creep-fatigue crack initiation and growth tests for a G91 tubular specimen including a machined defect have been performed by Kim and it was attempted to assess a high temperature crack behavior of Mod.9Cr-1Mo side plate specimen by Lee. The fatigue crack growth tests for Mod.9Cr-1Mo compact tension (CT) specimen were performed by Kim at some test conditions and further tests have been conducted at different test conditions 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
- 2010 autumn meeting of the KNS
- Dates
- 21-22 Oct 2010
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42084934
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKS; CREEP; DEFECTS; DESIGN; FATIGUE; HEAT EXCHANGERS; PIPES; REACTOR COMPONENTS; SODIUM COOLED REACTORS
- Descriptors DEC
- LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; TUBES
Optional Information
- Notes
- 8 refs, 5 figs, 2 tabs