Paper Title:
Effect of Heat Treatment on the Tensile Properties of Poly-Crystal and DS CM247LC Alloy
  Abstract

The effect of heat treatment in superalloy CM247LC on tensile properties at various temperatures has been investigated. In the case of equiaxed poly-crystal specimen, the aged condition (HTA condition) has higher strength than the solution treated and aged condition (HTSA condition) at low temperature. The HTSA condition exhibits higher strength than HTA condition in directionally solidified specimen in all temperature range. Shearing of γ´ particle is a principal deformation process at the low temperature, and cutting of fine secondary γ´ particle plays important role in the early stage of deformation in the HTA poly-crystal specimen. Tangles of short misfit dislocations form at the γ/γ´ interface during the high temperature deformation due to the partial loss of coherency at the interface. The rafting of γ´ increases tensile strength of the HTSA specimen at and above 871°C.

  Info
Periodical
Solid State Phenomena (Volumes 124-126)
Edited by
Byung Tae Ahn, Hyeongtag Jeon, Bo Young Hur, Kibae Kim and Jong Wan Park
Pages
1401-1404
DOI
10.4028/www.scientific.net/SSP.124-126.1401
Citation
I. S. Kim, B. G. Choi, S. M. Seo, D. H. Kim, C. Y. Jo, "Effect of Heat Treatment on the Tensile Properties of Poly-Crystal and DS CM247LC Alloy", Solid State Phenomena, Vols. 124-126, pp. 1401-1404, 2007
Online since
June 2007
Export
Price
$32.00
Share

In order to see related information, you need to Login.

In order to see related information, you need to Login.

Authors: Yan Ke Shi, Ke Shi Zhang, Jing Zhang, Ying Song Ma
Abstract:Based on the crystal plasticity theory, the slip-band traces on the specimen surface of polycrystalline copper tensioned uniaxially are...
1368
Authors: Xin Ming Cao, Wei Wei Guo, Xiao Wu Li
Abstract:The plastic deformation behavior of the and [014] Fe-35wt.%Cr alloy single crystals containing fine Cr-rich precipitates were investigated...
1960
Authors: I. Villacampa, Jia Chao Chen, Philippe Spätig, Hans Peter Seifert, F. Duval
Abstract:The most common fracture mechanism of nuclear reactor internals is irradiation-assisted stress corrosion cracking (IASCC). Its susceptibility...
228