Cluster dynamics modeling of Mn-Ni-Si precipitates in ferritic-martensitic steel under irradiation
Source abstract
Abstract
Mn-Ni-Si precipitates (MNSPs) are known to be responsible for irradiation-induced hardening and embrittlement in structural alloys used in nuclear reactors. Studies have shown that precipitation of the MNSPs in 9-Cr ferritic-martensitic (F-M) alloys, such as T91, is strongly associated with heterogeneous nucleation on dislocations, coupled with radiation-induced solute segregation to these sinks. Therefore it is important to develop advanced predictive models for Mn-Ni-Si precipitation in F-M alloys under irradiation based on an understanding of the underlying mechanisms. Here we use a cluster dynamics model, which includes multiple effects of dislocations, to study the evolution of MNSPs in a commercial F-M alloy T91. The model predictions are calibrated by data from proton irradiation experiments at 400 °C. Radiation induced solute segregation at dislocations is evaluated by a continuum model that is integrated into the cluster dynamics simulations, including the effects of dislocations as heterogeneous nucleation sites. The result shows that MNSPs in T91 are primarily irradiation-induced and, in particular, both heterogeneous nucleation and radiation-induced segregation at dislocations are necessary to rationalize the experimental observations.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (39)
Show source-provided references
1. Structural materials for fission & fusion energy10.1016/S1369-7021(09)70294-9 ↗
2. Emulation of reactor irradiation damage using ion beams10.1016/j.scriptamat.2014.06.003 ↗
3. Segregation behavior in proton- and heavy-ion-irradiated ferritic–martensitic alloys10.1016/j.actamat.2011.03.070 ↗
4. Radiation-induced segregation and phase stability in ferritic–martensitic alloy T 9110.1016/j.jnucmat.2010.12.052 ↗
5. Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys10.1016/j.jnucmat.2015.05.016 ↗
6. Radiation induced microstructural evolution in reactor pressure vessel steels10.1557/PROC-373-137 ↗
7. Evolution of manganese-nickel-silicon-dominated phases in highly irradiated reactor pressure vessel steels10.1016/j.actamat.2014.07.040 ↗
8. Predictive reactor pressure vessel steel irradiation embrittlement models: issues and opportunities10.1007/s11837-009-0097-4 ↗
9. Recent progress in understanding reactor pressure vessel steel embrittlement10.1080/10420159808229676 ↗
10. A systematic study of radiation-induced segregation in ferritic–martensitic alloys10.1016/j.jnucmat.2013.07.071 ↗
11. Phase stability in proton and heavy ion irradiated ferritic–martensitic alloys10.1016/j.jnucmat.2011.08.020 ↗
12. Thermodynamic models of low-temperature Mn-Ni-Si precipitation in reactor pressure vessel steels10.1557/mrc.2014.21 ↗
13. A lattice Monte Carlo simulation of nanophase compositions and structures in irradiated pressure vessel Fe-Cu-Ni-Mn-Si steels10.1016/S0921-5093(97)00450-4 ↗
14. A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels10.1016/S0022-3115(97)00267-5 ↗
15. Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels10.1016/j.actamat.2017.07.021 ↗
16. Monte Carlo study of decorated dislocation loops in FeNiMnCu model alloys10.1016/j.jnucmat.2014.05.051 ↗
17. Effect of neutron-irradiation on the microstructure of a Fe–12at.%Cr alloy10.1016/j.jnucmat.2011.05.042 ↗
18. Critical assessment of Cr-rich precipitates in neutron-irradiated Fe–12at%Cr: comparison of SANS and APT10.1016/j.jnucmat.2013.05.023 ↗
19. Behaviour of P, Si, Ni impurities and Cr in self ion irradiated Fe–Cr alloys – comparison to neutron irradiation10.1016/j.jnucmat.2014.10.024 ↗
20. Microstructural changes in a neutron-irradiated Fe–15at.%Cr alloy10.1016/j.jnucmat.2014.08.026 ↗
21. Slezov · 2009
22. Influence of cluster mobility on Cu precipitation in α-Fe: a cluster dynamics modeling10.1016/j.actamat.2010.02.014 ↗
23. Thermodynamic and kinetic modeling of oxide precipitation in nanostructured ferritic alloys10.1016/j.actamat.2015.03.014 ↗
24. On the effect of dose rate on irradiation hardening of RPV steels10.1080/14786430412331319910 ↗
25. Nucleation on dislocations10.1016/0001-6160(57)90021-4 ↗
26. A theory of radiation-induced segregation in concentrated alloys10.1016/0022-3115(79)90596-8 ↗
27. Drift forces on vacancies and interstitials in alloys with radiation-induced segregation10.1016/0022-3115(83)90268-4 ↗
28. Nucleation of a Second Solid-Phase Along Dislocations10.1007/BF02668009 ↗
29. Characterization of the intermetallic G-phase in an AISI 329 duplex stainless steel10.1023/A:1018669217124 ↗
30. M.Y. Lavrentiev, S.L. Dudarev, Chromium-vacancy Clusters in Dilute Bcc Fe-Cr Alloys: an Ab Initio Study. (arXiv:1703.02767v1 [cond-mat.mtrl-sci]).
31. Exact ab initio transport coefficients in bcc Fe-X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys10.1103/PhysRevB.90.104203 ↗
32. The theory of sink strengths10.1098/rsta.1981.0158 ↗
33. THERMO-CALC & DICTRA, computational tools for materials science10.1016/S0364-5916(02)00037-8 ↗
34. Microstructural evolution in annealed austenitic steels during neutron irradiation10.1179/095066087790150331 ↗
35. Phase stability of an HT-9 duct irradiated in FFTF10.1016/j.jnucmat.2012.06.038 ↗
36. Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443°C10.1016/j.jnucmat.2009.06.010 ↗
37. On the crystal structure of the Mn–Ni–Si G-phase10.1016/j.jallcom.2008.01.142 ↗
38. Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences10.1016/j.jnucmat.2013.01.312 ↗
39. A comparison of the structure of solute clusters formed during thermal ageing and irradiation10.1016/j.ultramic.2010.12.030 ↗