Effective enhancement of irradiation resistance in thermally aged FeCrAl alloys
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: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (75)
Show source-provided references
1. Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion10.1016/j.pnucene.2018.02.018 ↗
2. Generation-IV reactors and nuclear hydrogen production10.1016/j.ijhydene.2020.12.182 ↗
3. Neutronic evaluation of coating and cladding materials for accident tolerant fuels10.1016/j.pnucene.2015.11.006 ↗
4. High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments10.1016/j.jnucmat.2013.05.047 ↗
5. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions10.1016/j.jnucmat.2013.09.052 ↗
6. Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction10.1016/j.jnucmat.2013.12.022 ↗
7. Case studies on radioactivity and decay heat contribution from coating materials of irradiated accident tolerant fuel for a typical PHWR10.1016/j.nuclphysbps.2023.09.025 ↗
8. Realistic performance assessment of FeCrAl-UN/U3Si2 accident tolerant fuel under loss-of-coolant accident scenario10.1016/j.ress.2023.109847 ↗
9. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
10. Formation and stability of oxide layer in FeCrAl fuel cladding material under high-temperature steam10.1016/j.jallcom.2016.05.145 ↗
11. Theory-guided bottom-up design of the FeCrAl alloys as accident tolerant fuel cladding materials10.1016/j.jnucmat.2019.01.002 ↗
12. Steam oxidation evaluation of Fe–Cr alloys for accident tolerant nuclear fuel cladding10.1007/s11085-017-9754-0 ↗
13. Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments10.1016/j.jnucmat.2018.03.036 ↗
14. Nanocavity formation and hardness increase by dual ion beam irradiation of oxide dispersion strengthened FeCrAl alloy10.1016/j.jnucmat.2012.04.029 ↗
15. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors10.1016/j.anucene.2014.09.005 ↗
16. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding10.1016/j.jnucmat.2013.06.041 ↗
17. Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding10.1016/j.jnucmat.2017.12.035 ↗
18. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions10.1016/j.jnucmat.2017.04.039 ↗
19. Effects of ZrC addition on the microstructure and mechanical properties of Fe-Cr-Al alloys fabricated by spark plasma sintering10.1016/j.jallcom.2019.07.181 ↗
20. α′ precipitation in neutron-irradiated Fe–Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
21. A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys10.1016/j.actamat.2017.02.077 ↗
22. Sensitivity of thermo-electric power measurements to α–α′ phase separation in Cr-rich oxide dispersion strengthened steels10.1007/s10853-015-9014-0 ↗
23. SANS investigation of microstructure evolution in high chromium ODS steels after thermal ageing10.1016/j.jnucmat.2012.12.016 ↗
24. Microstructural stability of Fe–Cr–Al alloys at 450–550 °C10.1016/j.jnucmat.2014.11.101 ↗
25. Corrosion behavior of the FeCrAl coating with different Cr and Al contents before and after Au-ions irradiation in stagnant LBE10.1016/j.corsci.2023.111590 ↗
26. Effects of Cr element on the crystal structure, microstructure, and mechanical properties of FeCrAl alloys10.1016/j.msea.2021.142003 ↗
27. Effect of aluminum content on dislocation loops in model FeCrAl alloys
28. Mapping of 475 °C embrittlement in ferritic Fe–Cr–Al alloys10.1016/j.scriptamat.2010.08.015 ↗
29. New insights on the effects of chemistry and temperature on α’ precipitation during aging of FeCrAl alloys10.1016/j.jnucmat.2024.155542 ↗
30. Deconvoluting the effect of chromium and aluminum on the radiation response of wrought FeCrAl alloys after low-dose neutron irradiation10.1016/j.jnucmat.2021.152804 ↗
31. Phase separation kinetics in a Fe–Cr–Al alloy10.1016/j.actamat.2012.05.022 ↗
32. Regulating the dissolution of brittle nano-precipitated phase in FeCrAl alloy by pulse current to repair aging properties10.1016/j.matlet.2023.134633 ↗
33. 400 °C aging embrittlement of FeCrAl alloys: microstructure and fracture behavior10.1016/j.msea.2018.11.084 ↗
34. Effect of spinodal decomposition on the mechanical behavior of Fe–Cr alloys10.1016/j.msea.2010.01.020 ↗
35. The microstructure and property variations of metals induced by electric current treatment: a review10.1016/j.matchar.2018.08.058 ↗
36. Effect of aging and α’ segregation on oxidation and electrochemical behavior of FeCrAl alloys10.1016/j.jnucmat.2023.154751 ↗
37. Effects of thermal aging on the mechanical properties of FeCrAl-ODS alloy claddings10.2320/matertrans.MT-M2021057 ↗
38. Recovery, recrystallization and precipitation behavior in an ATF FeCrAl alloy during annealing treatment10.1016/j.matchar.2022.112026 ↗
39. Development of low-Cr wrought FeCrAl cladding alloys and its irradiation tolerance and steam oxidation resistance at 1200 °C10.1016/j.corsci.2021.109998 ↗
40. Microstructural control of FeCrAl alloys using Mo and Nb additions10.1016/j.matchar.2017.08.008 ↗
41. Effect of annealing temperature on the microstructure and mechanical properties of laves phase reinforced FeCrAl alloy thin-walled tubes10.1016/j.jnucmat.2022.153561 ↗
42. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
43. Establishment of multi-beam irradiation facility at Wuhan University10.1016/j.nima.2022.167202 ↗
44. J.F. Ziegler, M.D. Ziegler, J.P. Biersack, SRIM – The stopping and range of ions in matter (2010), Nucl. Instrum. Methods Phys. Res. B: Beam Interact. Mater. At. 268 (2010) 1818–1823. https://doi.org/10.1016/j.nimb.2010.02.091.10.1016/j.nimb.2010.02.091 ↗
45. On the use of SRIM for calculating vacancy production: quick calculation and full-cascade options10.1016/j.nimb.2021.06.018 ↗
46. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments10.1557/JMR.1992.1564 ↗
47. TEM characterization of dislocation loops in irradiated bcc Fe-based steels10.1016/j.jnucmat.2012.12.002 ↗
48. Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress10.1016/j.actamat.2007.09.016 ↗
49. h1 0 0i-Loop characterization in a-Fe: comparison between experiments and modeling10.1016/S0022-3115(02)01158-3 ↗
50. Interaction of 〈1 0 0〉 dislocation loops with dislocations studied by dislocation dynamics in α-iron10.1016/j.jnucmat.2015.01.061 ↗
51. Investigation of spatial relationship between helium bubbles and dislocation loops in RAFM steel10.1016/j.jnucmat.2021.152862 ↗
52. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations10.1016/j.jnucmat.2018.03.002 ↗
53. The indentation size effect: a critical examination of experimental observations and mechanistic interpretations10.1146/annurev-matsci-070909-104456 ↗
54. W.D. Nix, H. Gao, Size effects in crystalline : a law for strain gradient plasticity, (n.d.).
55. Understanding the effects of ion irradiation using nanoindentation techniques10.1016/j.jnucmat.2014.11.066 ↗
56. Characterization of ordered dislocation loop raft in Fe3+ irradiated pure iron at 300 °C10.1016/j.jnucmat.2018.09.020 ↗
57. In-situ TEM observation of the evolution of dislocation loops and helium bubbles in a pre helium irradiated FeCrAl alloy during annealing10.1016/j.pnucene.2020.103502 ↗
58. Micromechanical testing of unirradiated and helium ion irradiated SA508 reactor pressure vessel steels: nanoindentation vs in-situ microtensile testing10.1016/j.msea.2020.139942 ↗
59. In-situ TEM investigations of dislocation loop annealing kinetics in neutron-irradiated 9 %Cr RAFM steel
60. I.M. Robertson, M.A. Kirk, W.E. King, S. Goodwin, Formationof dislocationloopsin Iron by self-ion Irradiationsat 4ok, 18 (n.d.).10.1016/0036-9748(84)90444-7 ↗
61. Formation of ⟨100⟩ dislocation loop in bcc-Fe via the ternary loop reaction
62. Mechanism of formation and growth of ͗100͘ interstitial loops in ferritic materials10.1103/PhysRevLett.88.255507 ↗
63. Direct observation of the coalescence process between nanoscale dislocation loops with different Burgers vectors10.1016/j.actamat.2010.09.018 ↗
64. Indentation size effect in MgO10.1016/j.scriptamat.2004.05.034 ↗
65. Indentation size effect, geometrically necessary dislocations and pile-up effects in hardness testing of irradiated nickel10.1016/j.actamat.2021.116702 ↗
66. Radiation hardening revisited: role of intracascade clustering10.1016/S0022-3115(97)00231-6 ↗
67. A comparison study of change in hardness and microstructures of a Zr-added FeCrAl ODS steel irradiated with heavy ions10.1016/j.msea.2022.143050 ↗
68. Observation and analysis of defect cluster production and interactions with dislocations10.1016/j.jnucmat.2004.04.298 ↗
69. Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys10.1016/j.jnucmat.2014.01.024 ↗
70. Effect of Cr on the mechanical properties and microstructure of Fe–Cr model alloys after n-irradiation10.1016/j.jnucmat.2008.02.061 ↗
71. Radiation response of ODS ferritic steels with different oxide particles under ion-irradiation at 550 _C10.1016/j.jnucmat.2018.02.007 ↗
72. General relationship between strength and hardness10.1016/j.msea.2011.08.061 ↗
73. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys10.1016/j.jnucmat.2015.06.023 ↗
74. Martensite in steel: strength and structure10.1016/S0921-5093(99)00288-9 ↗
75. Evolution of microstructure and mechanical properties of 9Cr ferrite/martensite steels with different Si content after long-term aging at 550 °C10.1016/j.jallcom.2021.159817 ↗