Published October 2010 | Version v1
Miscellaneous

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

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
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