Radiation response of a Fe-20Cr-25Ni austenitic stainless steel under Fe2+ irradiation at 500 °C

被引:16
作者
Liu, Xiang [1 ,2 ]
Gigax, Jonathan G. [3 ]
Poplawsky, Jonathan D. [4 ]
Guo, Wei [4 ]
Kim, Hyosim [3 ]
Shao, Lin [3 ]
Garner, Frank A. [3 ,5 ]
Stubbins, James F. [1 ,6 ]
机构
[1] Univ Illinois, Dept Nucl Plasma & Radiol Engn, Urbana, IL 61801 USA
[2] Idaho Natl Lab, Characterizat & Adv PIE Div, Idaho Falls, ID 83415 USA
[3] Texas A&M Univ, Dept Nucl Engn, College Stn, TX 77843 USA
[4] Oak Ridge Natl Lab, Ctr Nanophase Mat Sci, POB 2009, Oak Ridge, TN 37831 USA
[5] Radiat Effects Consulting, Richland, WA 99354 USA
[6] Kyushu Univ, Int Inst Carbon Neutral Energy Res WPI I2CNER, Nishi Ku, 744 Motooka, Fukuoka 8190395, Japan
关键词
Ion irradiation; Transmission electron microscopy (TEM); Atom probe tomography (APT); Dislocation loops; Radiation-induced segregation; Irradiation hardening; MICROSTRUCTURAL EVOLUTION; INDUCED SEGREGATION; ION-IRRADIATION; YIELD-STRESS; PURE IRON; NEUTRON; TEMPERATURE; NF709; NANOINDENTATION; MICROHARDNESS;
D O I
10.1016/j.mtla.2019.100542
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The radiation response of a Fe-20Cr-25Ni austenitic stainless steel under self-ion irradiation at 500 degrees C was systematically investigated. The steel was irradiated at 500 degrees C by 3.5 MeV Fe2+ ions to 10, 50, and 150 peak dpa, respectively. In the 200-400 nm depth region, radiation-induced Frank loops were relatively stable in both size and number density from 10 to 150 peak dpa. Anisotropic distribution of Frank loops was observed in the 50 and 150 peak dpa specimens, possibly due to interaction of Frank loops and network dislocations with preferred orientations. Coarse voids were found only in the 50 and 150 peak dpa specimens in depths less than 750 nm, suggesting that injected interstitials at deeper regions suppressed the void nucleation. The peak swelling was very low (similar to 0.4%) for both 50 and 150 peak dpa irradiation. Radiation also led to the formation of intragranular plate-like Cr-rich carbides. Radiation-induced segregation of Ni and Si was found at various sinks: dislocation loops, void surfaces, and carbide-matrix interfaces. Finally, irradiation hardening was measured by nanoindentafion and the results are consistent with microstructure-based calculations using the dispersed barrier hardening model. The major contributor to irradiation hardening changed from Frank loops at the lowest dose to network dislocations at the highest dose.
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页数:13
相关论文
共 66 条
[51]   Thermophysical properties of Alloy 709 [J].
Smith, D. S. ;
Lybeck, N. J. ;
Wright, J. K. ;
Wright, R. N. .
NUCLEAR ENGINEERING AND DESIGN, 2017, 322 :331-335
[52]   Microstructural evolution in two variants of NF709 at 1023 and 1073 K [J].
Sourmail, T ;
Bhadeshia, HKDH .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2005, 36A (01) :23-34
[53]   On the use of SRIM for computing radiation damage exposure [J].
Stoller, R. E. ;
Toloczko, M. B. ;
Was, G. S. ;
Certain, A. G. ;
Dwaraknath, S. ;
Garner, F. A. .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2013, 310 :75-80
[54]  
Taylor C., 1983, DIMENS STAB MECH BEH, V1, P47, DOI DOI 10.1680/DSAMBOIMAAV1.01756.0012
[55]   In situ site-specific specimen preparation for atom probe tomography [J].
Thompson, K. ;
Lawrence, D. ;
Larson, D. J. ;
Olson, J. D. ;
Kelly, T. F. ;
Gorman, B. .
ULTRAMICROSCOPY, 2007, 107 (2-3) :131-139
[56]   Grain boundary segregation in neutron-irradiated 304 stainless steel studied by atom probe tomography [J].
Toyama, T. ;
Nozawa, Y. ;
Van Renterghem, W. ;
Matsukawa, Y. ;
Hatakeyama, M. ;
Nagai, Y. ;
Al Mazouzi, A. ;
Van Dyck, S. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 425 (1-3) :71-75
[57]   Microstructural defect evolution in neutron - Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing [J].
Tsay, K. V. ;
Maksimkin, O. P. ;
Turubarova, L. G. ;
Rofman, O. V. ;
Garner, F. A. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 439 (1-3) :148-158
[58]   A study on tensile properties of Alloy 709 at various temperatures [J].
Upadhayay, Swathi ;
Li, Hangyue ;
Bowen, Paul ;
Rabiei, Afsaneh .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 733 :338-349
[59]  
Was G.S., 2017, Fundamentals of Radiation Materials Science, DOI [10.1007/978-1-4939-3438-6, DOI 10.1007/978-1-4939-3438-6]
[60]   IRRADIATION-ASSISTED STRESS-CORROSION CRACKING IN AUSTENITIC ALLOYS [J].
WAS, GS ;
ANDRESEN, PL .
JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY, 1992, 44 (04) :8-13