Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties

被引:39
|
作者
Aydogan, E. [1 ,2 ]
Weaver, J. S. [1 ,3 ]
Carvajal-Nunez, U. [1 ]
Schneider, M. M. [1 ]
Gigax, J. G. [1 ]
Krumwiede, D. L. [4 ]
Hosemann, P. [4 ]
Saleh, T. A. [1 ]
Mara, N. A. [5 ]
Hoelzer, D. T. [6 ]
Hilton, B. [7 ]
Maloy, S. A. [1 ]
机构
[1] Los Alamos Natl Lab, Los Alamos, NM 87544 USA
[2] Sabanci Univ, Integrated Mfg Ctr, TR-34906 Istanbul, Turkey
[3] NIST, Gaithersburg, MD 20899 USA
[4] Univ Calif Berkeley, Berkeley, CA 94720 USA
[5] Univ Minnesota, Minneapolis, MN 55455 USA
[6] Oak Ridge Natl Lab, Oak Ridge, TN 37830 USA
[7] TerraPower LLC, Bellevue, WA 98005 USA
关键词
Nanostructured ferritic alloys (NFAs); Neutron irradiation; Nano-oxides (NOs); Alpha prime (alpha '); Radiation-induced hardening; RADIATION-INDUCED SEGREGATION; NANOSTRUCTURED FERRITIC ALLOYS; FE-CR ALLOYS; GRAIN-BOUNDARY CHARACTERISTICS; ENHANCED ALPHA' PRECIPITATION; TUBE PROCESSING METHODS; HEAVY-ION DAMAGE; DISLOCATION LOOPS; MARTENSITIC STEELS; ATOM-PROBE;
D O I
10.1016/j.actamat.2019.01.041
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Nanostructured ferritic alloys (NFAs) having sub-micron grain size with a high density of nano-oxides (NOs) (size of similar to 2-3 nm) are one of the best candidates for structural components in Generation IV nuclear systems. In this study, 14YWT NFA cladding tubes were irradiated in BOR60 reactor up to 7 dpa at 360-370 degrees C. Detailed microstructural analysis has been conducted using bright field transmission electron microscopy, bright field scanning transmission electron microscopy, energy filtered transmission electron microscopy, energy dispersive X-ray spectroscopy, electron energy loss spectroscopy and transmission Kikuchi diffraction techniques. This revealed cavities, <100> and <111> type dislocation loops, and alpha' precipitates forming after irradiation with relationships between cavities and NOs, and alpha' precipitates and NOs. Cavities mostly form on the NOs; whereas, alpha' precipitates form between the NOs where the point defect concentration is high. Moreover, alpha' precipitates are distributed homogenously on and around the dislocation loops which is consistent with the observation that there is no Cr segregation on dislocation loops. Grain boundaries were found to be mostly depleted in Cr; however, the characteristics of each grain boundary determines the Cr behavior and the alpha' denuded zone around the grain boundaries. Mechanical properties of the irradiated tubes have been determined by using both low force and high force nanoindentation techniques, resulting in 1.03 +/- 0.33 GPa and 0.82 +/- 0.20 GPa hardening, respectively. Dispersed barrier hardening calculations and nanoindentation measurements are in good agreement. In this study, 14YWT NFA has been systematically studied after neutron irradiation to better understand its superior performance: low alpha' concentration, low swelling and low radiation-induced hardening. (C) 2019 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码:181 / 196
页数:16
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