Superior irradiation resistance via nanocrystalline grains of 316L austenitic stainless steel
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (73)
Show source-provided references
1. Structural materials for fission & fusion energy10.1016/S1369-7021(09)70294-9 ↗
2. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
3. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure10.1016/S0022-3115(99)00225-1 ↗
4. The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D910.1016/j.actamat.2020.05.020 ↗
5. A promising new class of irradiation tolerant materials: ti2ZrHfV0.5Mo0.2 high-entropy alloy10.1016/j.jmst.2018.09.034 ↗
6. Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys10.1038/ncomms13564 ↗
7. Unusual size-dependent strengthening mechanisms in helium ion-irradiated immiscible coherent Cu/Co nanolayers10.1016/j.actamat.2014.10.061 ↗
8. Tuning the size-dependent He-irradiated tolerance and strengthening behavior of crystalline/amorphous Cu/Ta nanostructured multilayers10.1016/j.msea.2016.07.005 ↗
9. Austenitic oxide dispersion strengthened steels : a review10.14429/dsj.66.10205 ↗
10. Response of 9Cr-ODS steel to proton irradiation at 400 °C10.1016/j.jnucmat.2014.05.004 ↗
11. Damage-tolerant nanotwinned metals with nanovoids under radiation environments10.1038/ncomms8036 ↗
12. In-situ TEM characterization of the tensile deformation of ion-irradiated HT-UPS steel at RT and 400 °C10.1016/j.jnucmat.2019.151911 ↗
13. Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel10.1016/j.jnucmat.2018.04.043 ↗
14. In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation10.1016/j.actamat.2018.07.008 ↗
15. Radiation damage and thermal annealing in tunnel structured hollandite materials10.1016/j.actamat.2020.116598 ↗
16. A critical review on development, performance and selection of stainless steels and nickel alloys for the wet phosphoric acid process10.1016/j.matdes.2023.111739 ↗
17. Synthesis of nanomaterials using various top-down and bottom-up approaches, influencing factors, advantages, and disadvantages: a review10.1016/j.cis.2021.102597 ↗
18. Electrodeposited nanocrystals: synthesis, properties and industrial applications10.1016/0965-9773(95)00114-X ↗
19. Bulk nanostructured materials from severe plastic deformation10.1016/S0079-6425(99)00007-9 ↗
20. Microhardness and fracture properties of nanocrystalline Ni P alloy10.1016/0956-716X(90)90086-V ↗
21. The synthesis and structure of nanocrystalline materials produced by mechanical attrition: a review10.1016/0965-9773(93)90016-5 ↗
22. Nanostructured materials: basic concepts and microstructure10.1016/S1359-6454(99)00285-2 ↗
23. Efficient annealing of radiation damage near grain boundaries via interstitial emission10.1126/science.1183723 ↗
24. Effect of grain boundary character on sink efficiency10.1016/j.actamat.2012.08.009 ↗
25. Unprecedented irradiation resistance of nanocrystalline tungsten with equiaxed nanocrystalline grains to dislocation loop accumulation10.1016/j.actamat.2018.11.024 ↗
26. Zhang · 2012
27. In-situ TEM observation of the response of ultrafine- and nanocrystalline-grained tungsten to extreme irradiation environments10.1038/srep04716 ↗
28. Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments10.1038/srep07801 ↗
29. Ultrastrong nanocrystalline steel with exceptional thermal stability and radiation tolerance10.1038/s41467-018-07712-x ↗
30. Was · 2017
31. Williams · 2008
32. Quantitative measurement of displacement and strain fields from HREM micrographs10.1016/S0304-3991(98)00035-7 ↗
33. Microstructure and texture evolution during cold rolling of 316L stainless steel10.1007/s11661-021-06367-6 ↗
34. Effects of initial 3D printed microstructures on subsequent microstructural evolution in 316L stainless steel10.1016/j.actamat.2022.118481 ↗
35. Enhanced radiation-tolerant oxide dispersion strengthened steel and its microstructure evolution under helium-implantation and heavy-ion irradiation
36. Nanocrystalline zirconia can Be amorphized by ion irradiation10.1103/PhysRevLett.88.025503 ↗
37. Impact of irradiation on the microstructure of nanocrystalline materials10.1016/j.jnucmat.2004.04.058 ↗
38. Microstructure of hardened and softened zirconia after xenon implantation10.1557/JMR.1991.1905 ↗
39. Thermal stability of ultrafine grained Fe–Cr–Ni alloy10.1016/j.msea.2012.02.033 ↗
40. Thermal and mechanical stability of Austenite in metastable austenitic stainless steel10.1007/s11661-019-05362-2 ↗
41. Nitrogen enhances microstructural thermal stability of Si-modified Fe-Cr-Ni austenitic stainless steel10.1016/j.jmst.2024.11.027 ↗
42. Surface roughening and grain orientation dependence of the erosion of polycrystalline stainless steel by hydrogen irradiation10.1016/j.jnucmat.2004.04.240 ↗
43. Grain orientation dependence of nanoindentation and deformation-induced martensitic phase transformation in neutron irradiated AISI 304L stainless steel10.1016/j.mtla.2019.100208 ↗
44. Grain growth in nanocrystalline metal thin films under In situ ion-beam irradiation10.1520/JAI100743 ↗
45. A thermal spike model of grain growth under irradiation10.1063/1.2988142 ↗
46. Dislocation decoration and raft formation in irradiated materials10.1080/14786430500154281 ↗
47. Microstructural evolution of NF709 austenitic stainless steel under in-situ ion irradiations at room temperature, 300, 400, 500 and 600 °C10.1016/j.jnucmat.2018.07.044 ↗
48. In-situ TEM observation of loop evolution in Mo-5Re alloy under Fe+ irradiation10.1016/j.jnucmat.2021.153443 ↗
49. Three-dimensional maps of helium nanobubbles to probe the mechanisms of bubble nucleation and growth10.1021/acs.jpcc.9b00709 ↗
50. Influence of chemical disorder on energy dissipation and defect evolution in concentrated solid solution alloys10.1038/ncomms9736 ↗
51. Modeling irradiation-induced intragranular gas bubble in tungsten under external tensile loading10.1016/j.ijrmhm.2022.105824 ↗
52. In-situ studies on the mechanical properties of He ion irradiated nanotwinned Ag10.1016/j.jnucmat.2020.152392 ↗
53. An in situ study on the effect of grain boundaries on helium bubble formation in dual beam irradiated FeCrAl alloy10.1016/j.actamat.2022.118613 ↗
54. Grain size effects on He bubbles distribution and evolution10.1016/j.jnucmat.2014.11.036 ↗
55. The role of grain size in He bubble formation: implications for swelling resistance10.1016/j.jnucmat.2016.12.003 ↗
56. Microstructure of ion irradiated ceramic insulators10.1016/0168-583X(94)96224-3 ↗
57. Quantifying grain boundary damage tolerance with atomistic simulations10.1088/0965-0393/24/7/075011 ↗
58. Evidence of a temperature transition for denuded zone formation in nanocrystalline Fe under He irradiation10.1080/21663831.2016.1243591 ↗
59. On the absorption of dislocations by grain boundaries
60. Grain boundary strain as a determinant of localized sink efficiency10.1016/j.actamat.2022.117624 ↗
61. Effect of grain boundary stresses on sink strength10.1080/21663831.2013.871588 ↗
62. Hirth · 1992
63. Ultra-wide void denuded zone near composite grain boundary in micro-nano crystalline 304L steels10.1016/j.scriptamat.2023.115497 ↗
64. Void denuded zone formation for Fe–15Cr–15Ni steel and PNC316 stainless steel under neutron and electron irradiations10.1016/j.jnucmat.2014.12.054 ↗
65. Neon-concentration dependent retarding effect on the recrystallization of irradiated tungsten: experimental analysis and molecular dynamics simulation10.1016/j.jmst.2022.09.031 ↗
66. Vacancy accumulation mechanism at iron grain boundaries: the influence of grain boundary character and its coupling with grain size10.1016/j.jnucmat.2023.154386 ↗
67. The effect of grain size on bubble formation and evolution in helium-irradiated Cu-Fe-Ag10.1016/j.matchar.2020.110822 ↗
68. In situ evidence of defect cluster absorption by grain boundaries in Kr ion irradiated nanocrystalline Ni10.1007/s11661-013-1635-9 ↗
69. Direct observation of sink-dependent defect evolution in nanocrystalline iron under irradiation10.1038/s41598-017-01744-x ↗
70. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel10.1016/0022-3115(93)90128-L ↗
71. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
72. Radiation resistance of nano-crystalline iron: coupling of the fundamental segregation process and the annihilation of interstitials and vacancies near the grain boundaries10.1016/j.actamat.2016.02.028 ↗
73. Mechanisms of radiation-induced segregation around He bubbles in a Fe-Cr-Ni crystal10.1016/j.jnucmat.2018.11.030 ↗