Impact of micro-alloying in ion-irradiated nickel: From the inhibition of point-defect cluster diffusion by thermal segregation to the change of dislocation loop nature

被引:17
作者
Ma, Kan [1 ,7 ]
Decamps, Brigitte [2 ]
Huang, Liangzhao [1 ]
Schaublin, Robin E. [3 ]
Loffler, Jorg F. [3 ]
Fraczkiewicz, Anna [4 ]
Nastar, Maylise
Prima, Frederic [5 ]
Loyer-Prost, Marie [1 ,6 ]
机构
[1] Univ Paris Saclay, CEA, Serv Rech Met Phys, F-91191 Gif Sur Yvette, France
[2] Univ Paris Saclay, CNRS, IN2P3, Lab Phys 2 Infinis Irene Joliot Curie IJCLab, F-91400 Orsay, France
[3] Swiss Fed Inst Technol, Dept Mat, Lab Met Phys & Technol, Vladimir Prelog Weg 4, CH-8093 Zurich, Switzerland
[4] Univ Lyon, Ctr SMS, MINES St Etienne, CNRS,UMR 5307,LGF, F-42023 St Etienne, France
[5] PSL Res Univ, CNRS, Inst Rech Chim Paris, Chim ParisTech, Paris, France
[6] CEA Saclay, DES, ISAS, DMN,SRMP,JANNUS, PC 162, F-91191 Gif Sur Yvette, France
[7] Univ Birmingham, Sch Met & Mat, Birmingham B15 2TT, England
关键词
Irradiation; Micro-alloying; Dislocation loop nature; Radiation-induced segregation; Thermodynamics; FE-CR-NI; RADIATION-INDUCED SEGREGATION; ELECTRON-MICROSCOPE; SWELLING BEHAVIOR; INTERSTITIAL LOOPS; PHASE-STABILITY; MODEL ALLOYS; GROWTH; DAMAGE; COPPER;
D O I
10.1016/j.actamat.2022.118656
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Micro-alloying strongly affects the incubation period of void swelling in irradiated face-centered cubic materials. However, the underlying mechanism, which relates to the formation of dislocation loops, is still unclear. Here, we investigate pure Ni, Ni-0.4wt.%Cr and Ni-0.4/0.8/1.2wt.%Ti as model materials, to gain insight into the solute effects on the loops evolution in the early stage of irradiation. The dislocation loop characteristics (mobility, Burgers vector, nature) are studied using in-situ transmission electron microscopy and ex-situ irra-diation with Ni+ ions at 450 degrees C and 510 degrees C for doses from 0.06 to 0.7 dpa. It appears that a tiny amount of Ti effectively increases the loop density, reduces the loop mobility and the stacking fault energy. It leads to an equal distribution among a/2 < 110 > perfect loop families. It also stabilizes self-interstitial loops against vacancy loops depending on Ti content and temperature. Our modeling of radiation-induced segregation, based on experiments and recent ab initio calculations of flux couplings, predicts a Cr enrichment and a Ti depletion nearby dislocation loops. It is in good agreement with our observations by X-ray spectroscopy in TEM and by atom probe tomog-raphy. However, the lowered loop mobility must be the signature of a thermal segregation rather than the impact of radiation-induced depletion. Indeed, oversized Ti atoms subsequently trapped at strained lattice sites around the dislocation line of the loop due to thermal segregation would inhibit its diffusion. This opens new per-spectives for future experimental investigations and radiation-effect modeling.
引用
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页数:19
相关论文
共 79 条
[1]   IRRADIATION-INDUCED SWELLING IN COMMERCIAL ALLOYS [J].
BATES, JF ;
POWELL, RW .
JOURNAL OF NUCLEAR MATERIALS, 1981, 102 (1-2) :200-213
[2]   Effect of chromium on void swelling in ion irradiated high purity Fe-Cr alloys [J].
Bhattacharya, A. ;
Meslin, E. ;
Henry, J. ;
Barbu, A. ;
Poissonnet, S. ;
Decamps, B. .
ACTA MATERIALIA, 2016, 108 :241-251
[3]   In situ transmission electron microscopy investigation of radiation effects [J].
Birtcher, RC ;
Kirk, MA ;
Furuya, K ;
Lumpkin, GR ;
Ruault, MO .
JOURNAL OF MATERIALS RESEARCH, 2005, 20 (07) :1654-1683
[4]   RATE THEORY OF SWELLING DUE TO VOID GROWTH IN IRRADIATED METALS [J].
BRAILSFORD, AD ;
BULLOUGH, R .
JOURNAL OF NUCLEAR MATERIALS, 1972, 44 (02) :121-+
[5]   Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injection [J].
Brimbal, Daniel ;
Decamps, Brigitte ;
Henry, Jean ;
Meslin, Estelle ;
Barbu, Alain .
ACTA MATERIALIA, 2014, 64 :391-401
[6]   VOIDS IN NEUTRON IRRADIATED FACE CENTERED CUBIC METALS [J].
BRIMHALL, JL ;
MASTEL, B .
JOURNAL OF NUCLEAR MATERIALS, 1969, 29 (01) :123-&
[7]  
Bullough R., 1981, Dislocation Modelling of Physical Systems, P116, DOI DOI 10.1016/B978-0-08-026724-1.50017-0
[8]   Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels [J].
Busby, JT ;
Was, GS ;
Kenik, EA .
JOURNAL OF NUCLEAR MATERIALS, 2002, 302 (01) :20-40
[9]   Effect of saddle point anisotropy of point defects on their absorption by dislocations and cavities [J].
Carpentier, D. ;
Jourdan, T. ;
Le Bouar, Y. ;
Marinica, M. -C. .
ACTA MATERIALIA, 2017, 136 :323-334
[10]  
Carpentier D., 2018, THESIS U PARIS SACLA