2014
DOI: 10.1016/j.matdes.2013.08.007
|View full text |Cite
|
Sign up to set email alerts
|

Effect of α–α′ phase separation on notch impact behavior of oxide dispersion strengthened (ODS) Fe20Cr5Al alloy

Abstract: a b s t r a c tThe effects of Fe-rich (a) and Cr-enriched (a 0 ) phase separation, occurring during aging at 475°C on the microstructure and mechanical properties of Fe-20Cr-6Al ODS alloy (PM2000™) hot-rolled tube, were investigated by means of atom probe tomography, microhardness, tensile and V-notched Charpy impact tests. Disregarding of the aging treatment, this material presents splitting of crack-divider type in longitudinal-transverse (LT) specimens, whereas crack-arrester type is observed in longitudina… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
5

Citation Types

0
6
0

Year Published

2015
2015
2024
2024

Publication Types

Select...
9

Relationship

0
9

Authors

Journals

citations
Cited by 41 publications
(6 citation statements)
references
References 38 publications
0
6
0
Order By: Relevance
“…Fe-Cr-Al alloys have good corrosion resistance, radiation resistance, and mechanical strength, and they are being developed as structural materials for the next generation of nuclear reactors, such as fusion reactors, sodium fast reactors, lead-cooled fast reactors, and supercritical water reactors [1][2][3][4][5]. Also, because of the comprehensive performance of Fe-Cr-Al alloys in steam environments, these alloys are under consideration for accident-tolerant fuel-cladding applications [6][7][8].…”
Section: Introductionmentioning
confidence: 99%
“…Fe-Cr-Al alloys have good corrosion resistance, radiation resistance, and mechanical strength, and they are being developed as structural materials for the next generation of nuclear reactors, such as fusion reactors, sodium fast reactors, lead-cooled fast reactors, and supercritical water reactors [1][2][3][4][5]. Also, because of the comprehensive performance of Fe-Cr-Al alloys in steam environments, these alloys are under consideration for accident-tolerant fuel-cladding applications [6][7][8].…”
Section: Introductionmentioning
confidence: 99%
“…The outstanding material performance stems from their unique microstructure: the highly stable nano-sized oxide particles [9,10]. It was reported that high content of chromium (>13%) in the ODS alloys is effective to suppress corrosion [11,12], while the high chromium content (>14%) can result in a thermal aging embrittlement [13,14]. Some researchers have reported the effectiveness of Al addition in ODS ferritic alloys for the improvement of corrosion resistance in Lead-cooled fast reactor (LFR) and supercritical water reactor (SCWR) [15,16,17].…”
Section: Introductionmentioning
confidence: 99%
“…Fe-Cr-based stainless steels are used in nuclear power plants for their good oxidation resistance, corrosion resistance, and mechanical properties [6,7]. At present, Fe-Cr-Al alloys have been developed as structural materials for nextgeneration nuclear reactors, such as fusion reactors, sodium fast reactors, lead-cooled fast reactors, and supercritical water reactors [8][9][10]. To further improve the properties of Fe-Cr-Al alloys, alloying elements were often added, for example adding Y element to improve the oxidation resistance [11], adding Mo and Nb elements to cause grain refinement and solid solution hardening to strengthen the bcc-Fe matrix [12], and adding Ti element to form a TiAlrich nanoscale precipitation to improve creep resistance [13].…”
Section: Introductionmentioning
confidence: 99%