Skip to main content
Fachgebiete
Automobil + Motoren Bauwesen + Immobilien Business IT + Informatik Elektrotechnik + Elektronik Energie + Nachhaltigkeit Finance + Banking Management + Führung Marketing + Vertrieb Maschinenbau + Werkstoffe Versicherung + Risiko
DE
EN
Themenseiten
Organisationspsychologie Projektmanagement Marketing Smart Manufacturing
Bücher
Zeitschriften
Weitere Formate
Podcasts Webinare Technik Webinare Wirtschaft Kongresse Veranstaltungskalender Awards
Jetzt Einzelzugang starten
Zugang für Unternehmen
Referenzkunden
MTZ-Fachkongress

Antriebe und Energiesysteme von morgen


Austausch von Automobil- und Energiewirtschaft

Am 14./15. Mai geht es in Chemnitz um die Mobilitätswende durch Elektro- und Wasserstofffahrzeuge.
Erweiterte Suche
Anmelden
nach oben
Journal of Materials Engineering and Performance
Erschienen in: Journal of Materials Engineering and Performance 3/2022

03.11.2021

Effect of Ion Irradiation on Surface Microstructure and Nano-Hardness of SA508-IV Reactor Pressure Vessel Steel

verfasst von: Xue Bai, Yun Han, Peter K. Liaw, Lijun Wei

Erschienen in: Journal of Materials Engineering and Performance | Ausgabe 3/2022

Einloggen

Aktivieren Sie unsere intelligente Suche, um passende Fachinhalte oder Patente zu finden.

search-config
loading …

Abstract

A new type SA508-IV reactor pressure vessel steel was irradiated at 290 °C to 3 and 30 displacement per atom (dpa) with 3.5 MeV Fe2+ ions. The focused ion beam was used to cut the samples for the field emission transmission electron microscope (FE-TEM) after irradiation. The microstructure analysis under the scanning transmission electron microscope (STEM) mode of FE-TEM revealed that the heavy ion irradiation produced a large number of matrix defects and Cu-rich clusters. The high dosage of irradiation would also force Mo atoms to relocate to form Cr/Mn/Mo-rich precipitates. Dislocation loops were especially formed in samples irradiated by 30 dpa, which are one of the principal evolving defects in irradiated materials. The nanoindentation test results showed that the nano-hardness increases with the increase of irradiation doses. The semi-plateau stage in 3 dpa irradiation (I3 sample) curve of nano-hardness versus indentation depth corresponds to the saturation of Cu-rich clusters; while the plateau stage in the I30 sample curve should be attributed to the loop coalescence.
Vorheriger Artikel Unusual Rolling Texture in Ferritic/Martensitic Steel
Nächster Artikel Extrusion of Light and Ultralight Alloys with Liquid Nitrogen Conformal Cooled Dies: Process Analysis and Simulation

Sie haben noch keine Lizenz? Dann Informieren Sie sich jetzt über unsere Produkte:

Springer Professional "Wirtschaft+Technik"

Online-Abonnement

Mit Springer Professional "Wirtschaft+Technik" erhalten Sie Zugriff auf:

  • über 102.000 Bücher
  • über 537 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Finance + Banking
  • Management + Führung
  • Marketing + Vertrieb
  • Maschinenbau + Werkstoffe
  • Versicherung + Risiko

Jetzt Wissensvorsprung sichern!

Jetzt informieren

Springer Professional "Technik"

Online-Abonnement

Mit Springer Professional "Technik" erhalten Sie Zugriff auf:

  • über 67.000 Bücher
  • über 390 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Maschinenbau + Werkstoffe




 

Jetzt Wissensvorsprung sichern!

Jetzt informieren
Literatur
1.
T.R. Leax, Temperature Dependence and Variability of Fracture Thoughness in the Transition Regime for A508 Grade 4N Pressure Vessel Steel, J. ASTM Int., 2006, 3(1), p 1–20. CrossRef
2.
G.L. Wire, W.J. Beggs, T.R. Leax, Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other Low-Alloy Steels, Bettis Atomic Power Laboratory (BAPL), West Mifflin, PA, USA, 2002, B-T-3450
3.
Y. Zhou, J. Chen, Y. Xu and Z. Liu, Effects of Cr, Ni and Cu on the Corrosion Behavior of Low Carbon Microalloying Steel in a CF-Containing Environment, J. Mater. Sci. Technol., 2013, 29, p 168–174. CrossRef
4.
Y.T. Chen, D.G. Atteridge and W.W. Gerberich, Plastic Flow of Fe-Binary Alloys-I. A Description at Low Temperatures, Acta Metall., 1981, 29(6), p 1171–1185. CrossRef
5.
W.W. Gerberich, Y.T. Chen, D.G. Atteridge and T. Johnson, Plastic flow of Fe-binary alloys-II. Application of the description to the ductile-brittle transition, Acta Metall., 1981, 29(6), p 1187–1201. CrossRef
6.
S. Konovalov, Y. Ivanov, V. Gromov and I. Panchenko, Fatigue-induced Evolution of AISI 310S Steel Microstructure after Electron Beam Treatment, Materials, 2020, 13(20), p 1–13. CrossRef
7.
P.P. Liu, M.Z. Zhao, Y.M. Zhu, J.W. Bai, F.R. Wan and Q. Zhan, Effects of Carbide Precipitate on the Mechanical Properties and Irradiation Behavior of the Low Activation Martensitic Steel, J. Alloy. Compd., 2013, 579(5), p 599–605. CrossRef
8.
G.S. Was, J.T. Busby, T. Allen, E.A. Kenik, A. Jenssen, S.M. Bruemmer, J. Gan, A.D. Edwards, P.M. Scott and P.L. Andresen, Emulation of Neutron Irradiation Effects With Protons: Validation of Principle, J. Nucl. Mater., 2002, 300(2–3), p 198–216. CrossRef
9.
G. Gupta, Z. Jiao, A.N. Ham, J.T. Busby and G.S. Was, Microstructural Evolution of Proton Irradiated T91, J. Nucl. Mater., 2006, 351(1–3), p 162–173. CrossRef
10.
C. Sun, S. Zheng, C.C. Wei, Y. Wu, L. Shao, Y. Yang, K.T. Hartwig, S.A. Maloy, S.J. Zinkle, T.R. Allen, H. Wang and X. Zhang, Superior Radiation-Resistant Nanoengineered Austenitic 304L Stainless Steel for Applications in Extreme Radiation Environments, Sci. Rep., 2015, 5, p 7801–7807. CrossRef
11.
S.J. Wu and L.W. Cao, Effect of Intergranular Failure on the Critical Fracture Stress and the Fracture Toughness of Degraded Reactor Pressure Vessel Steel, Int. J. Press. Ves. Pip., 2013, 101, p 23–29. CrossRef
12.
B. Radiguet, P. Pareige and A. Barbu, Irradiation Induced Clustering in Low Copper or Copper Free Ferritic Model Alloys, Nucl. Instrum. Methods Phys. Res. B, 2009, 267(8–9), p 1496–1499. CrossRef
13.
B. Yang, Thermographic Detection of Fatigue Damage of Reactor Pressure Vessel (RPV) Steels, J. Mater. Eng. Perform., 2003, 12(3), p 345–353. CrossRef
14.
K. Fujii, K. Fukuya and T. Hojo, Concomitant Formation of Different Nature Clusters and Hardening in Reactor Pressure Vessel Steels Irradiated by Heavy Ions, J. Nucl. Mater., 2013, 443(1–3), p 378–385. CrossRef
15.
F. Hori, A. Morita and R. Oshima, Radiation-Enhanced Precipitation in FeCu(C) Alloys Studied by Electron Microscopy, J. Electron Microsc., 1999, 48(5), p 585–589. CrossRef
16.
G.R. Odette, Radiation Induced Microstructral Evolution in Reactor Pressure Vessel Steels, Mat. Res. Soc. Symp. Proc., 1995, 373, p 137–148. CrossRef
17.
G.R. Odette and G.E. Lucas, Radiat. Eff. Defects Solids, 1998, 144, p 189–231. CrossRef
18.
T. Toyama, N. Tsuchiya, Y. Nagai, A. Almazouzi, M. Hatakeyama, M. Hasegawa, T. Ohkubo, E. van Walle and R. Gerard, Irradiation- Induced Changes of the Atomic Distributions around the Interfaces of Carbides in a Nuclear Reactor Pressure Vessel Steel, J. Nucl. Mater., 2010, 405, p 177–180. CrossRef
19.
X.D. Li and B. Bhushan, A Review of Nanoindentation Continuous Stiffness Measurement Technique and its Applications, Mater. Charact., 2002, 48, p 11–36. CrossRef
20.
M. Chausov, P. Maruschak, A. Pylypenko and L. Markashova, Enhancing Plasticity of High-Strength Titanium Alloys VT 22 Under Impact-Oscillatory Loading, Phil. Mag., 2017, 97(6), p 389–399. CrossRef
21.
J.F. Ziegler, J.P. Biersack and U. Littmark, The Stopping and Range of Ions in Solids, Pergamon Press, New York, USA, Treatise on Heavy-Ion Science, 1985, p 93–129
22.
X. Bai, S.J. Wu and P.K. Liaw, Influence of Thermo-Mechanical Embrittlement Processing on Microstructure and Mechanical Behavior of a Pressure Vessel Steel, Mater. Des., 2016, 89, p 759–769. CrossRef
23.
R.L. Klueh, N. Hashimoto, M.A. Sokolov, K. Shiba and S. Jitsukawa, Mechanical Properties of Neutron-Irradiated Nickel-Containing Martensitic Steels: I. Experimental Study, J. Nucl. Mater., 2006, 357(1–3), p 156–168. CrossRef
24.
R.L. Klueh, N. Hashimoto, M.A. Sokalov, P.J. Maziasz, K. Shiba and S. Jitsukawa, Mechanical Properties of Neutron-Irradiated Nickel-Containing Martensitic Steels: II. Review and Analysis of Helium-Effects Studies, J. Nucl. Mater., 2006, 357(1–3), p 169–182. CrossRef
25.
Y. Nishiyama, K. Onizawa, M. Suzuki, J.W. Anderegg, Y. Nagai, T. Toyama, M. Hasegawa and J. Kameda, Effects of Neutron-Irradiation-Induced Intergranular Phosphorus Segregation and Hardening on Embrittlement in Reactor Pressure Vessel Steels, Acta Mater., 2008, 56(16), p 4510–4521. CrossRef
26.
H. Shibamoto, K. Kitao, H. Matsui, M. Hasegawa, S. Yamaguchi and A. Kimura, Effect of Nickel on Irradiation Hardening and Microstructure Evolution of Proton Irradiated Fe-Cu Alloys, Effects of radiation on materials, 20th international symposium, ASTM STP 1405. S.T. Rosinski, M.L. Grossbeck, T.R. Allen, A.S. Kumar Ed., American Society for Testing and Materials, PA, USA, West Conshohocken, 2001, p 722–733
27.
H. Watanabe, S. Arase, T. Yamamoto, P. Wells, T. Onishi and G.R. Odette, Hardening and Microstructural Evolution of A533b Steels Irradiated with Fe Ions and Electrons, J. Nucl. Mater., 2016, 471, p 243–250. CrossRef
28.
T. Sharma, N.N. Kumar, R. Mondal, K.V.M. Krishna, I. Samajdar and V. Kain, Ductile-to-Brittle Transition in Low-Alloy Steel: A Combined Experimental and Numerical Investigation, J. Mater. Eng. Perform., 2019, 28(7), p 4275–4288. CrossRef
29.
A. Gandhi, A. Kundu, A. Sarkar, J.K. Mahato and P.C. Chakraborti, Effect of Laser Pulse Duration on Tensile and Electrochemical Behavior of Laser-Welded Dual-Phase Steel, J. Mater. Eng. Perform., 2021, 30(6), p 4263–4281. CrossRef
30.
M.K. Miller, K.F. Russell, P. Pareige, M.J. Starink and R.C. Thomson, Low Temperature Copper Solubilities in Fe-Cu-Ni, Mater. Sci. Eng. A, 1998, 250(1), p 49–54. CrossRef
31.
G. Salje and M. Feller-Kniepmeir, The Diffusion and Solubility of Copper in Iron, J. Appl. Phys., 1977, 48(5), p 1833–1839. CrossRef
32.
B. Radiguet, A. Barbu and P. Pareige, Understanding of Copper Precipitation Under Electron or Ion Irradiations in FeCu0.1wt% Ferritic Alloy by Combination of Experiments and Modelling, J. Nucl. Mater., 2007, 360(2), p 104–117. CrossRef
33.
E. Vincent, C.S. Becquart and C. Domain, Ab Initio Calculations of Self-Interstitial Interaction and Migration with Solute Atoms in bcc Fe, J. Nucl. Mater., 2006, 359(3), p 227–237. CrossRef
34.
G.R. Odette and G.E. Lucas, Embrittlement of Nuclear Reactor Pressure Vessels, JOM, 2001, 53(7), p 18–22. CrossRef
35.
D.Y. Lee, E.V. Barrera, J.P. Stark and H.L. Marcus, The Influence of Alloying Elements on Impurity Induced Grain Boundary Embrittlement, Metall. Trans. A, 1984, 15A, p 1415–1430. CrossRef
36.
J. Kameda and Y. Nishiyama, Combined Effects of Phosphorus Segregation and Partial Intergranular Fracture on the Ductile-Brittle Transition Temperature in Structural Alloy Steels, Mater. Sci. Eng. A, 2011, 528, p 3705–3713. CrossRef
37.
E. Meslin, B. Radiguet and M. Loyer-Prost, Radiation-Induced Precipitation in a Ferritic Model Alloy: An Experimental and Theoretical Study, Acta Mater., 2013, 61, p 6246–6254. CrossRef
38.
T. Muroga, H. Watanabe and N. Yoshida, Correlation of Fast Neutron, Fusion Neutron and Electron Irradiations based on the Dislocation Loop Density, J. Nucl. Mater., 1990, 174, p 282–288. CrossRef
39.
C.D. Hardie, C.A. Williams, S. Xu and S.G. Roberts, Effects of Irradiation Temperature and Dose Rate on the Mechanical Properties of Self-Ion Implanted Fe and Fe-Cr Alloys, J. Nucl. Mater., 2013, 439, p 33–40. CrossRef
40.
J. Bohmert, H.W. Viehrig and A. Ulbricht, Correlation Between Irradiation-Induced Changes of Microstructural Parameters and Mechanical Properties of RPV Steels, J. Nucl. Mater., 2004, 334(1), p 71–78. CrossRef
41.
J. Jiang, Y.C. Wu, X.B. Liu, R.S. Wang, Y. Nagai, K. Inoue, Y. Shimizu and T. Toyama, Microstructural Evolution of RPV Steels Under Proton and Ion Irradiation Studied by Positron Annihilation Spectroscopy, J. Nucl. Mater., 2015, 458, p 326–334. CrossRef
42.
X. Bai, S.J. Wu, P.K. Liaw, L. Shao and J. Gigax, Effect of Heavy Ion Irradiation Dosage on the Hardness of SA508-IV Reactor Pressure Vessel Steel, Metals, 2017, 7(25), p 1–11.
43.
P.G. Sanders, J.A. Eastman and J.R. Weertman, Elastic and Tensile Behavior of Nanocrystalline Copper and Palladium, Acta Mater., 1997, 45(10), p 4019–4025. CrossRef
Metadaten
Titel
Effect of Ion Irradiation on Surface Microstructure and Nano-Hardness of SA508-IV Reactor Pressure Vessel Steel
verfasst von
Xue Bai
Yun Han
Peter K. Liaw
Lijun Wei
Publikationsdatum
03.11.2021
Verlag
Springer US
Erschienen in
Journal of Materials Engineering and Performance / Ausgabe 3/2022
Print ISSN: 1059-9495
Elektronische ISSN: 1544-1024
DOI
https://doi.org/10.1007/s11665-021-06376-x

Weitere Artikel der Ausgabe 3/2022

Journal of Materials Engineering and Performance 3/2022 Zur Ausgabe

OriginalPaper

Characterization of Tool Wear Mechanisms and Failure Modes of TiAlN-NbN Coated Carbide Inserts in Face Milling of Inconel 718

OriginalPaper

Microbiologically Influenced Corrosion of AA 6061 with Bacillus Species in an Environment Containing an Organic Nitrogen Source

OriginalPaper

Influence of Ultrasonic Shot Peening on Microstructure, Mechanical, and Electrochemical Behavior of 316 Stainless Steel

OriginalPaper

Effect of Heat Treatment on Corrosion Performance of Mg-12Gd-3Y-1Sm-0.8Al Alloy

OriginalPaper

Effects of Solution Heat Treatment Temperatures on Microstructures and Mechanical Properties of SP-700 Ti Alloys

OriginalPaper

Process Optimization of Planetary Rolling of Bismuth-Containing Austenitic Stainless Steel

Premium Partner

    Marktübersichten

    Die im Laufe eines Jahres in der „adhäsion“ veröffentlichten Marktübersichten helfen Anwendern verschiedenster Branchen, sich einen gezielten Überblick über Lieferantenangebote zu verschaffen. 

    Zur Marktübersicht
    Bildnachweise