Published October 2007 | Version v1
Miscellaneous

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

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
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