4D evolution of Cr23C6 precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography

Nori, Sri Tapaswi; Bengoa, Alejandro Figueroa; Thomas, Jonova; Hunter, James; Kenesei, Peter; Park, Jun-Sang; Almer, Jonathan; Okuniewski, Maria A.

doi:10.1557/s43578-021-00474-1

4D evolution of Cr₂₃C₆ precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography

Journal Article · Wed Jan 12 23:00:00 EST 2022 · Journal of Materials Research

DOI:https://doi.org/10.1557/s43578-021-00474-1· OSTI ID:1869700

Nori, Sri Tapaswi ^[1]; Bengoa, Alejandro Figueroa ^[1]; Thomas, Jonova ^[1]; Hunter, James ^[2]; Kenesei, Peter ^[3]; Park, Jun-Sang ^[3]; Almer, Jonathan ^[3]; ^[1]

Purdue Univ., West Lafayette, IN (United States)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Argonne National Lab. (ANL), Argonne, IL (United States)

High-temperature-ultrafine precipitate strengthened (HT-UPS) steel is a potential structural material for advanced nuclear reactors; however, its irradiation response is not well understood. This research provides insight into irradiation-induced effects, such as precipitate evolution mechanisms and four-dimensional morphological evolution, in HT-UPS steel using synchrotron micro-computed tomography. Identical specimens were characterized pre-irradiation and post-irradiation following neutron exposure up to 0.3 displacements per atom at 600 °C. Irradiation effects were also differentiated from the annealing response of precipitates. Following neutron irradiation, the average Cr₂₃C₆ precipitate size reduced, affected by the synergy of nucleation and growth, ballistic dissolution, and inverse coarsening, which was observed at fluences an order of magnitude lower than previously observed. Annealing at 600 °C for 32 h increased the average Cr₂₃C₆ precipitate size and decreased the phase fraction, attributed to precipitate coarsening. The precipitate morphology evolution and resultant mechanisms can be utilized to parameterize and validate microstructural models simulating radiation damage or annealing.

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: Purdue University; U. S. Nuclear Regulatory Commission (NRC); USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1869700

Journal Information:: Journal of Materials Research, Journal Name: Journal of Materials Research Journal Issue: 1 Vol. 37; ISSN 0884-2914

Publisher:: Materials Research SocietyCopyright Statement

Country of Publication:: United States

Language:: English

References (42)

Kinetics of Materials Balluffi, Robert W.; Allen, Samuel M.; Carter, W. Craig https://doi.org/10.1002/0471749311	book	September 2005
Theorie der Alterung von Niederschlägen durch Umlösen (Ostwald‐Reifung) Wagner, Carl Zeitschrift für Elektrochemie, Berichte der Bunsengesellschaft für physikalische Chemie, Vol. 65, Issue 7-8 https://doi.org/10.1002/BBPC.19610650704	journal	September 1961
Fundamentals of Radiation Materials Science Was, Gary S. https://doi.org/10.1007/978-1-4939-3438-6	book	January 2017
Developing an austenitic stainless steel for improved performance in advanced fossil power facilities Maziasz, Philip J. JOM, Vol. 41, Issue 7 https://doi.org/10.1007/BF03220265	journal	July 1989
Development of Creep-Resistant and Oxidation-Resistant Austenitic Stainless Steels for High Temperature Applications Maziasz, Philip J. JOM, Vol. 70, Issue 1 https://doi.org/10.1007/s11837-017-2642-x	journal	November 2017
Void-swelling and precipitation in a neutron-irradiated, niobium-stabilised austenitic stainless steel Williams, T. M.; Titchmarsh, J. M.; Arkell, D. R. Journal of Nuclear Materials, Vol. 107, Issue 2-3 https://doi.org/10.1016/0022-3115(82)90423-8	journal	June 1982
Reduction of helium embrittlement in stainless steel by finely dispersed TiC precipitates Kesternich, W.; Rothaut, J. Journal of Nuclear Materials, Vol. 104 https://doi.org/10.1016/0022-3115(82)90705-X	journal	January 1981
Coprecipitation of M23C6 and MC type carbide under the influence of irradiation Kesternich, W.; Nandedkar, R. V. Journal of Nuclear Materials, Vol. 179-181 https://doi.org/10.1016/0022-3115(91)90263-7	journal	March 1991
Overview of microstructural evolution in neutron-irradiated austenitic stainless steels Maziasz, P. J. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90077-C	journal	October 1993
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel Zinkle, S. J.; Maziasz, P. J.; Stoller, R. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90128-L	journal	November 1993
The influence of radiation-induced segregation on precipitate stability in austenitic steels Pechenkin, V. A.; Epov, G. A. Journal of Nuclear Materials, Vol. 207 https://doi.org/10.1016/0022-3115(93)90273-2	journal	December 1993
Phase transformations under irradiation Wollenberger, H. Journal of Nuclear Materials, Vol. 216 https://doi.org/10.1016/0022-3115(94)90007-8	journal	October 1994
The kinetics of precipitation from supersaturated solid solutions Lifshitz, I. M.; Slyozov, V. V. Journal of Physics and Chemistry of Solids, Vol. 19, Issue 1-2 https://doi.org/10.1016/0022-3697(61)90054-3	journal	April 1961
Precipitation of M23C6 type carbide on twin boundaries in austenitic stainless steels Terao, N.; Sasmal, B. Metallography, Vol. 13, Issue 2 https://doi.org/10.1016/0026-0800(80)90010-5	journal	April 1980
The effect of cold work on the precipitation kinetics of an advanced austenitic steel Todd, J. A.; Ren, Jyh-Ching Materials Science and Engineering: A, Vol. 117 https://doi.org/10.1016/0921-5093(89)90106-8	journal	September 1989
Correlation of the M23C6 precipitation morphology with grain boundary characteristics in austenitic stainless steel Hong, H. U.; Rho, B. S.; Nam, S. W. Materials Science and Engineering: A, Vol. 318, Issue 1-2 https://doi.org/10.1016/S0921-5093(01)01254-0	journal	November 2001
In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation Xu, Chi; Zhang, Xuan; Chen, Yiren Acta Materialia, Vol. 156 https://doi.org/10.1016/j.actamat.2018.07.008	journal	September 2018
Numerical simulation of long-term precipitate evolution in austenitic heat-resistant steels Shim, Jae-Hyeok; Kozeschnik, Ernst; Jung, Woo-Sang Calphad, Vol. 34, Issue 1 https://doi.org/10.1016/j.calphad.2010.01.001	journal	March 2010
Creep behavior of a new cast austenitic alloy Shingledecker, John P.; Maziasz, Philip J.; Evans, Neal D. International Journal of Pressure Vessels and Piping, Vol. 84, Issue 1-2 https://doi.org/10.1016/j.ijpvp.2006.09.014	journal	January 2007
Characterization of neutron-irradiated HT-UPS steel by high-energy X-ray diffraction microscopy Zhang, Xuan; Park, Jun-Sang; Almer, Jonathan Journal of Nuclear Materials, Vol. 471 https://doi.org/10.1016/j.jnucmat.2015.11.063	journal	April 2016
Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel Xu, Chi; Chen, Wei-Ying; Zhang, Xuan Journal of Nuclear Materials, Vol. 507 https://doi.org/10.1016/j.jnucmat.2018.04.043	journal	August 2018
Numerical simulation of grain boundary carbides evolution in 316H stainless steel Xiong, Qingrong; Robson, Joseph D.; Chang, Litao Journal of Nuclear Materials, Vol. 508 https://doi.org/10.1016/j.jnucmat.2018.05.074	journal	September 2018
Microstructural evolution of NF709 austenitic stainless steel under in-situ ion irradiations at room temperature, 300, 400, 500 and 600 °C Xu, Chi; Chen, Wei-Ying; Chen, Yiren Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.044	journal	October 2018
The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel Thomas, Jonova; Figueroa Bengoa, Alejandro; Nori, Sri Tapaswi Journal of Nuclear Materials, Vol. 537 https://doi.org/10.1016/j.jnucmat.2020.152161	journal	August 2020
Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation Nori, Sri Tapaswi; Park, Gyuchul; Williams, Walter Journal of Nuclear Materials, Vol. 554 https://doi.org/10.1016/j.jnucmat.2021.153056	journal	October 2021
Effects of ageing conditions on the precipitates evolution, chromium depletion and intergranular corrosion susceptibility of AISI 316L: experimental and modeling results Sahlaoui, H.; Makhlouf, K.; Sidhom, H. Materials Science and Engineering: A, Vol. 372, Issue 1-2 https://doi.org/10.1016/j.msea.2003.12.017	journal	May 2004
Fatigue and creep–fatigue deformation of an ultra-fine precipitate strengthened advanced austenitic alloy Carroll, M. C.; Carroll, L. J. Materials Science and Engineering: A, Vol. 556 https://doi.org/10.1016/j.msea.2012.07.082	journal	October 2012
Recent developments in stainless steels Lo, K. H.; Shek, C. H.; Lai, J. K. L. Materials Science and Engineering: R: Reports, Vol. 65, Issue 4-6 https://doi.org/10.1016/j.mser.2009.03.001	journal	May 2009
Ion irradiation-induced precipitation of Cr23C6 at dislocation loops in austenitic steel Jin, Shuoxue; Guo, Liping; Luo, Fengfeng Scripta Materialia, Vol. 68, Issue 2 https://doi.org/10.1016/j.scriptamat.2012.10.002	journal	January 2013
3D quantitative analysis of graphite morphology in high strength cast iron by high-energy X-ray tomography Chuang, Chihpin; Singh, Dileep; Kenesei, Peter Scripta Materialia, Vol. 106 https://doi.org/10.1016/j.scriptamat.2015.03.017	journal	September 2015
X-ray computed tomography Withers, Philip J.; Bouman, Charles; Carmignato, Simone Nature Reviews Methods Primers, Vol. 1, Issue 1 https://doi.org/10.1038/s43586-021-00015-4	journal	February 2021
On the possibilities of x‐ray phase contrast microimaging by coherent high‐energy synchrotron radiation Snigirev, A.; Snigireva, I.; Kohn, V. Review of Scientific Instruments, Vol. 66, Issue 12 https://doi.org/10.1063/1.1146073	journal	December 1995
Nucleation and growth instabilities of precipitates induced under irradiation Kesternich, W. Philosophical Magazine A, Vol. 77, Issue 1 https://doi.org/10.1080/01418619808214234	journal	January 1998
Radiation-induced segregation and precipitate stability in austenitic stainless steels Pechenkin, V. A.; Epov, G. A. Plasma Devices and Operations, Vol. 3, Issue 1-2 https://doi.org/10.1080/10519999408201809	journal	March 1994
Active contours without edges Chan, T. F.; Vese, L. A. IEEE Transactions on Image Processing, Vol. 10, Issue 2 https://doi.org/10.1109/83.902291	journal	January 2001
Creep-Resistant, Al2O3-Forming Austenitic Stainless Steels Yamamoto, Y.; Brady, M. P.; Lu, Z. P. Science, Vol. 316, Issue 5823 https://doi.org/10.1126/science.1137711	journal	April 2007
Marching cubes: A high resolution 3D surface construction algorithm Lorensen, William E.; Cline, Harvey E. Proceedings of the 14th annual conference on Computer graphics and interactive techniques - SIGGRAPH '87 https://doi.org/10.1145/37401.37422	conference	January 1987
Precipitation in creep resistant austenitic stainless steels Sourmail, T. Materials Science and Technology, Vol. 17, Issue 1 https://doi.org/10.1179/026708301101508972	journal	January 2001
Compatibility Assessment of Advanced Stainless Steels in Sodium Pawel, S. J. Fusion Science and Technology, Vol. 61, Issue 1T https://doi.org/10.13182/FST12-A13447	journal	January 2012
Using Analytical Electron Microscopy to Design Radiation Resistant Steels for Fusion Applications Maziasz, P. J.; Klueh, R. L.; Rowcliffe, A. F. MRS Bulletin, Vol. 14, Issue 7 https://doi.org/10.1557/S088376940006214X	journal	July 1989
Efficient N-Dimensional surface estimation using Crofton formula and run-length encoding Lehmann, Gaetan; Legland, David The Insight Journal https://doi.org/10.54294/wdu86d	journal	February 2012
A Survey: Image Segmentation Techniques [A Survey: Image Segmentation Techniques] Waseem Khan, Muhammad International Journal of Future Computer and Communication https://doi.org/10.7763/IJFCC.2014.V3.274	journal	January 2014

Similar Records

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

Journal Article · Tue May 11 00:00:00 EDT 2021 · Journal of Nuclear Materials · OSTI ID:1837087

Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel

Journal Article · Tue May 01 00:00:00 EDT 2018 · Journal of Nuclear Materials · OSTI ID:1455049

In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation

Journal Article · Fri Jul 06 00:00:00 EDT 2018 · Acta Materialia · OSTI ID:1482550

Related Subjects

36 MATERIALS SCIENCE
X-ray tomography
annealing
neutron irradiation
nuclear materials
radiation effects
steel

4D evolution of Cr23C6 precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography

Citation Formats

References (42)

Similar Records

Related Subjects

4D evolution of Cr₂₃C₆ precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography