Oxide dispersoid coherency of a ferritic-martensitic 12Cr oxide-dispersion-strengthened alloy under self-ion irradiation

Kim, Hyosim; Gigax, Jonathan Gregory; Ukai, Shigeharu; Garner, Frank A.; Shao, Lin

doi:10.1016/j.jnucmat.2020.152671

Title: Oxide dispersoid coherency of a ferritic-martensitic 12Cr oxide-dispersion-strengthened alloy under self-ion irradiation

Journal Article · Fri Nov 13 00:00:00 EST 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152671· OSTI ID:1726198

^[1];

^[1]; Ukai, Shigeharu ^[2]; Garner, Frank A. ^[3]; Shao, Lin ^[3]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Hokkaido Univ., Sapporo (Japan)
Texas A & M Univ., College Station, TX (United States)

Ferritic-martensitic oxide-dispersion-strengthened (ODS) alloy has shown excellent mechanical property and high radiation tolerance. However, the stability of dispersoids during displacive irradiation in the individual ferritic and martensitic phases is unclear. In this work, the correlation among dispersoid coherency, size, density, and matrix phase are studied in dual-phase 12Cr ODS after 100 peak displacements-per-atom (dpa) irradiation at 475°C, using 3.5 MeV Fe²⁺ self-ions. The size and density changes of coherent and incoherent dispersoids were analyzed as a function of irradiation depth. The average dispersoid size decreased after irradiation in both phases, and the large incoherent dispersoids in the tempered martensite phase underwent a more dramatic change than those in the ferrite phase. The dispersoid density significantly increased in the ferrite phase within the irradiated region, mostly resulting in an increase in coherent dispersoid density. On the other hand, only a small change in density was observed in the tempered martensite phase for both coherent and incoherent dispersoids. This study shows that dispersoid evolution is dramatically different in ferrite and tempered martensite phases.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); National Science Foundation (NSF)

Grant/Contract Number:: 89233218CNA000001; 1708788

OSTI ID:: 1726198

Report Number(s):: LA-UR-20-23227; TRN: US2205467

Journal Information:: Journal of Nuclear Materials, Vol. 544, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (36)

Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys Klueh, R. L.; Shingledecker, J. P.; Swindeman, R. W. Journal of Nuclear Materials, Vol. 341, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2005.01.017	journal	May 2005
Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy Ramar, A.; Spätig, P.; Schäublin, R. Journal of Nuclear Materials, Vol. 382, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2008.08.009	journal	December 2008
Development of oxide dispersion strengthened ferritic steels for fusion Mukhopadhyay, D. K.; Froes, F. H.; Gelles, D. S. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00188-3	journal	October 1998
Recent Developments in Irradiation-Resistant Steels Odette, G. R.; Alinger, M. J.; Wirth, B. D. Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503 https://doi.org/10.1146/annurev.matsci.38.060407.130315	journal	August 2008
Hardness of 12Cr8Mo ferritic steels irradiated by Ni ions Ohta, J.; Ohmura, T.; Kako, K. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(95)00016-X	journal	August 1995
On the Zener drag Nes, E.; Ryum, N.; Hunderi, O. Acta Metallurgica, Vol. 33, Issue 1 https://doi.org/10.1016/0001-6160(85)90214-7	journal	January 1985
Radiation instability of equal channel angular extruded T91 at ultra-high damage levels Gigax, Jonathan G.; Kim, Hyosim; Chen, Tianyi Acta Materialia, Vol. 132 https://doi.org/10.1016/j.actamat.2017.04.038	journal	June 2017
The threshold stress and departure side pinning of dislocations by dispersoids Nardone, V. C.; Matejczyk, D. E.; Tien, J. K. Acta Metallurgica, Vol. 32, Issue 9 https://doi.org/10.1016/0001-6160(84)90097-X	journal	September 1984
High Temperature Materials for Nuclear Fast Fission and Fusion Reactors and Advanced Fossil Power Plants Jayakumar, T.; Mathew, M. D.; Laha, K. Procedia Engineering, Vol. 55 https://doi.org/10.1016/j.proeng.2013.03.252	journal	January 2013
Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications Odette, G. R. JOM, Vol. 66, Issue 12 https://doi.org/10.1007/s11837-014-1207-5	journal	November 2014
The stability of precipitates in an irradiation environment Nelson, R. S.; Hudson, J. A.; Mazey, D. J. Journal of Nuclear Materials, Vol. 44, Issue 3 https://doi.org/10.1016/0022-3115(72)90043-8	journal	September 1972
Perspective of ODS alloys application in nuclear environments Ukai, Shigeharu; Fujiwara, Masayuki Journal of Nuclear Materials, Vol. 307-311, p. 749-757 https://doi.org/10.1016/S0022-3115(02)01043-7	journal	December 2002
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel Klueh, R. L.; Maziasz, P. J.; Kim, I. S. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01046-2	journal	December 2002
Refinement of Oxide Particles by Addition of Hf in Ni-0.5 mass%Al-1 mass%Y₂O₃ Alloys Tang, Qingxin; Hoshino, Takeshi; Ukai, Shigeharu MATERIALS TRANSACTIONS, Vol. 51, Issue 11 https://doi.org/10.2320/matertrans.M2010163	journal	January 2010
Effect of Helium on Dispersoid Evolution under Self-Ion Irradiation in A Dual-Phase 12Cr Oxide-Dispersion-Strengthened Alloy Kim, Hyosim; Wang, Tianyao; Gigax, Jonathan G. Materials, Vol. 12, Issue 20 https://doi.org/10.3390/ma12203343	journal	October 2019
Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences Mansur, L. K.; Rowcliffe, A. F.; Nanstad, R. K. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.016	journal	August 2004
Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions Shao, Lin; Wei, C. -C.; Gigax, J. Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.002	journal	October 2014
SRIM – The stopping and range of ions in matter (2010) Ziegler, James F.; Ziegler, M. D.; Biersack, J. P. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12 https://doi.org/10.1016/j.nimb.2010.02.091	journal	June 2010
Interfacial strained structure and orientation relationships of the nanosized oxide particles deduced from elasticity-driven morphology in oxide dispersion strengthened materials Ribis, J.; de Carlan, Y. Acta Materialia, Vol. 60, Issue 1 https://doi.org/10.1016/j.actamat.2011.09.042	journal	January 2012
Residual ferrite formation in 12CrODS steels Ukai, S.; Kudo, Y.; Wu, X. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.09.038	journal	December 2014
On the use of SRIM for computing radiation damage exposure Stoller, R. E.; Toloczko, M. B.; Was, G. S. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310 https://doi.org/10.1016/j.nimb.2013.05.008	journal	September 2013
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C Gigax, Jonathan G.; Aydogan, Eda; Chen, Tianyi Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.05.025	journal	October 2015
Dispersoid stability in ion irradiated oxide-dispersion-strengthened alloy Kim, Hyosim; Gigax, Jonathan G.; Chen, Tianyi Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.015	journal	October 2018
Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling Gigax, Jonathan G.; Kim, Hyosim; Aydogan, Eda Materials Research Letters, Vol. 5, Issue 7 https://doi.org/10.1080/21663831.2017.1323808	journal	May 2017
Radiation response of alloy T91 at damage levels up to 1000 peak dpa Gigax, J. G.; Chen, T.; Kim, Hyosim Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.003	journal	December 2016
Nano-mesoscopic structure control in 9Cr–ODS ferritic steels Ukai, S.; Ohtsuka, S. Energy Materials, Vol. 2, Issue 1 https://doi.org/10.1179/174892407X210357	journal	March 2007
Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces Chen, Tianyi; Gigax, Jonathan G.; Price, Lloyd Acta Materialia, Vol. 116 https://doi.org/10.1016/j.actamat.2016.05.042	journal	September 2016
The effect of oxide particle coherency on Zener pinning in ODS superalloys Mujahid, M.; Martin, J. W. Journal of Materials Science Letters, Vol. 13, Issue 3 https://doi.org/10.1007/BF00278146	journal	January 1994
Improvement of Creep Strength of 9CrODS Martensitic Steel by Controlling Excess Oxygen and Titanium Concentrations Ohtsuka, Satoshi; Ukai, Shigeharu; Fujiwara, Masayuki MATERIALS TRANSACTIONS, Vol. 46, Issue 3 https://doi.org/10.2320/matertrans.46.487	journal	January 2005
Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation Chen, Tianyi; Aydogan, Eda; Gigax, Jonathan G. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.09.016	journal	December 2015
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure Garner, F. A.; Toloczko, M. B.; Sencer, B. H. Journal of Nuclear Materials, Vol. 276, Issue 1-3 https://doi.org/10.1016/S0022-3115(99)00225-1	journal	January 2000
Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials Shao, Lin; Gigax, Jonathan; Chen, Di Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 409 https://doi.org/10.1016/j.nimb.2017.05.026	journal	October 2017
Vacancy Mechanism of High Oxygen Solubility and Nucleation of Stable Oxygen-Enriched Clusters in Fe Fu, C. L.; Krčmar, Maja; Painter, G. S. Physical Review Letters, Vol. 99, Issue 22 https://doi.org/10.1103/PhysRevLett.99.225502	journal	November 2007
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations Zinkle, S. J.; Snead, L. L. Scripta Materialia, Vol. 143 https://doi.org/10.1016/j.scriptamat.2017.06.041	journal	January 2018
Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9 Gigax, Jonathan G.; Kim, Hyosim; Aydogan, E. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 444 https://doi.org/10.1016/j.nimb.2018.12.051	journal	April 2019
Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing Ukai, Shigeharu; Nishida, Toshio; Okada, Hirokazu Journal of Nuclear Science and Technology, Vol. 34, Issue 3 https://doi.org/10.1080/18811248.1997.9733658	journal	March 1997

Similar Records

Towards High Performance Oxide-Dispersion-Strengthened Alloys

Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1726198

Chen, Tianyi; Kim, Hyosim; Gigax, Jonathan; +4 more

Effect of helium on dispersoid evolution under self-ion irradiation in a dual-phase 12Cr oxide-dispersion-strengthened alloy

Journal Article · Mon Oct 14 00:00:00 EDT 2019 · Materials · OSTI ID:1726198

Kim, Hyosim; Gigax, Jonathan Gregory; Wang, Tianyao; +3 more

Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ≈295 °C to ≈6.5 dpa

Journal Article · Thu Aug 06 00:00:00 EDT 2015 · Journal of Nuclear Materials · OSTI ID:1726198

Maloy, Stuart A.; Saleh, Tarik A.; Anderoglu, Osman; +6 more

Related Subjects

36 MATERIALS SCIENCE

Title: Oxide dispersoid coherency of a ferritic-martensitic 12Cr oxide-dispersion-strengthened alloy under self-ion irradiation

Citation Formats

References (36)

Similar Records

Related Subjects