Effect of Chromium Content on Mechanical Properties and Microstructural Evolution of Ion-Irradiated Fe-Cr Model Alloys
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Fe-Cr alloy of a ferritic martensitic microstrucuture is one of the candidate structural materials for fusion reactor steels. It is well known that Fe-Cr alloys have a high resistance to a swelling and an excellent resistance to a helium embrittlement and to irradiation creep. But it has a severe problem about low temperature irradiation-induced embrittlement below 673K. The mechanical behavior of an irradiated material is mostly affected by the formation of irradiation induced defects called black dots, a dislocation loop and a void in the matrix. The main objective of this present study is to investigate the effect of chromium content on the irradiated hardening behavior of a polycrystalline Fe-Cr alloy. We measured a hardness change with a Nano indenter for irradiated Fe-Cr alloys and analyzed the size and fraction of the irradiation induced defects with a transmission electron microscopy
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
- 2007 autumn meeting of the KNS
- Dates
- 25-26 Oct 2007
- Place
- Pyongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39077754
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DEFECTS; IRON ALLOYS; MECHANICAL PROPERTIES; MICROSTRUCTURE; REACTORS; SWELLING; TRANSMISSION ELECTRON MICROSCOPY
- Descriptors DEC
- ALLOYS; DEFORMATION; ELECTRON MICROSCOPY; MICROSCOPY; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 5 refs, 5 figs