Details
| Original language | English |
|---|---|
| Pages (from-to) | 484-490 |
| Number of pages | 7 |
| Journal | Journal of nuclear materials |
| Volume | 443 |
| Issue number | 1-3 |
| Publication status | Published - 16 Aug 2013 |
Abstract
Creep was studied in Haynes 230, a material candidate for the very high temperature reactor's intermediate heat exchanger, at 800°C and 900°C. This study focused on the differences between the behavior at the two elevated temperature, and using the microstructure, grain boundary serrations and triple junction strain concentrations were quantitatively identified. There was significant damage in the 900°C samples and the creep was almost entirely tertiary. In contrast, the 800°C sample exhibited secondary creep. Using an Arrhenius equation, the minimum creep rate exponents were found to be n ≈ 3 and n ≈ 5 for 900°C and 800°C, respectively. The creep mechanisms were identified as solute drag for n ≈ 3 and dislocation climb for n ≈ 5. Strain concentrations were identified at triple junctions and grain boundary serrations using high resolution digital image correlation overlaid on the microstructure. The grain boundary serrations restrict grain boundary sliding which may reduce the creep damage at triple junctions and extend the creep life of Haynes 230 at elevated temperatures.
ASJC Scopus subject areas
- Physics and Astronomy(all)
- Nuclear and High Energy Physics
- Materials Science(all)
- General Materials Science
- Energy(all)
- Nuclear Energy and Engineering
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In: Journal of nuclear materials, Vol. 443, No. 1-3, 16.08.2013, p. 484-490.
Research output: Contribution to journal › Article › Research › peer review
}
TY - JOUR
T1 - Creep deformation and mechanisms in Haynes 230 at 800°C and 900°C
AU - Pataky, Garrett J.
AU - Sehitoglu, Huseyin
AU - Maier, Hans J.
PY - 2013/8/16
Y1 - 2013/8/16
N2 - Creep was studied in Haynes 230, a material candidate for the very high temperature reactor's intermediate heat exchanger, at 800°C and 900°C. This study focused on the differences between the behavior at the two elevated temperature, and using the microstructure, grain boundary serrations and triple junction strain concentrations were quantitatively identified. There was significant damage in the 900°C samples and the creep was almost entirely tertiary. In contrast, the 800°C sample exhibited secondary creep. Using an Arrhenius equation, the minimum creep rate exponents were found to be n ≈ 3 and n ≈ 5 for 900°C and 800°C, respectively. The creep mechanisms were identified as solute drag for n ≈ 3 and dislocation climb for n ≈ 5. Strain concentrations were identified at triple junctions and grain boundary serrations using high resolution digital image correlation overlaid on the microstructure. The grain boundary serrations restrict grain boundary sliding which may reduce the creep damage at triple junctions and extend the creep life of Haynes 230 at elevated temperatures.
AB - Creep was studied in Haynes 230, a material candidate for the very high temperature reactor's intermediate heat exchanger, at 800°C and 900°C. This study focused on the differences between the behavior at the two elevated temperature, and using the microstructure, grain boundary serrations and triple junction strain concentrations were quantitatively identified. There was significant damage in the 900°C samples and the creep was almost entirely tertiary. In contrast, the 800°C sample exhibited secondary creep. Using an Arrhenius equation, the minimum creep rate exponents were found to be n ≈ 3 and n ≈ 5 for 900°C and 800°C, respectively. The creep mechanisms were identified as solute drag for n ≈ 3 and dislocation climb for n ≈ 5. Strain concentrations were identified at triple junctions and grain boundary serrations using high resolution digital image correlation overlaid on the microstructure. The grain boundary serrations restrict grain boundary sliding which may reduce the creep damage at triple junctions and extend the creep life of Haynes 230 at elevated temperatures.
UR - http://www.scopus.com/inward/record.url?scp=84883818518&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2013.08.009
DO - 10.1016/j.jnucmat.2013.08.009
M3 - Article
AN - SCOPUS:84883818518
VL - 443
SP - 484
EP - 490
JO - Journal of nuclear materials
JF - Journal of nuclear materials
SN - 0022-3115
IS - 1-3
ER -