Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions

Tan, Lizhen; Stoller, Roger E.; Field, Kevin G.; Yang, Ying; Morgan, Dane; Wirth, Brian D.; Gussev, Maxim N.; Busby, Jeremy T.; Nam, H.

doi:10.1007/s11837-015-1753-5

Title: Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions

Journal Article · Thu Dec 10 23:00:00 EST 2015 · JOM. Journal of the Minerals, Metals & Materials Society

DOI: https://doi.org/10.1007/s11837-015-1753-5 · OSTI ID:1236587

Tan, Lizhen ^[1]; Stoller, Roger E. ^[1]; Field, Kevin G. ^[1]; Yang, Ying ^[1]; Morgan, Dane ^[2]; Wirth, Brian D. ^[3]; Gussev, Maxim N. ^[1]; Busby, Jeremy T. ^[1]; Nam, H. ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Wisconsin, Madison, WI (United States)
Univ. of Tennessee, Knoxville, TN (United States)

Extension of light water reactors' useful life will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), which will lead to profound microstructural evolution and consequent degradation of macroscopic properties. Microstructural evolution, including Frank loops, cavities, precipitates, and segregation at boundaries and the resultant radiation hardening in type 304 and 316 stainless steel (SS) variants, were studied in this work via experimental characterization and multiple simulation methods. Experimental data for up to 40 heats of type 304SS and 316SS variants irradiated in different reactors to 0.6–120 dpa at 275–375°C were either generated from this work or collected from literature reports. These experimental data were then combined with models of Frank loop and cavity evolution, computational thermodynamics and precipitation, and ab initio and rate theory integrated radiation-induced segregation models to provide insights into microstructural evolution and degradation at higher radiation doses.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1236587

Journal Information:: JOM. Journal of the Minerals, Metals & Materials Society, Journal Name: JOM. Journal of the Minerals, Metals & Materials Society Journal Issue: 2 Vol. 68; ISSN 1047-4838

Publisher:: SpringerCopyright Statement

Country of Publication:: United States

Language:: English

References (46)

Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C Yang, Yong; Chen, Yiren; Huang, Yina Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors https://doi.org/10.1007/978-3-319-48760-1_128	book	January 2011
The Effect of Chemical Composition and Heat Treatment Conditions on Stacking Fault Energy for Fe-Cr-Ni Austenitic Stainless Steel Yonezawa, Toshio; Suzuki, Ken; Ooki, Suguru Metallurgical and Materials Transactions A, Vol. 44, Issue 13 https://doi.org/10.1007/s11661-013-1943-0	journal	August 2013
Radiation damage concerns for extended light water reactor service Allen, T. R.; Busby, J. T. JOM, Vol. 61, Issue 7 https://doi.org/10.1007/s11837-009-0099-2	journal	July 2009
A theory of radiation-induced segregation in concentrated alloys Wiedersich, H.; Okamoto, P. R.; Lam, N. Q. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90596-8	journal	August 1979
Compositional changes in Fe-Cr-Ni alloys under proton bombardment at elevated temperatures Lam, N. Q. Journal of Nuclear Materials, Vol. 117 https://doi.org/10.1016/0022-3115(83)90015-6	journal	July 1983
Radiation Damage in Austenitic Steels Garner, F. A. Comprehensive Nuclear Materials https://doi.org/10.1016/B978-0-08-056033-5.00065-3	book	January 2012
Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel Duh, T. S.; Kai, J. J.; Chen, F. R. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00255-5	journal	December 2000
On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials Stoller, R. E.; Zinkle, S. J. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00378-0	journal	December 2000
Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels Duh, T. S.; Kai, J. J.; Chen, F. R. Journal of Nuclear Materials, Vol. 294, Issue 3 https://doi.org/10.1016/S0022-3115(01)00493-7	journal	April 2001
Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C Edwards, D. J.; Simonen, E. P.; Bruemmer, S. M. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/S0022-3115(03)00002-3	journal	April 2003
Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS Edwards, D. J.; Simonen, E. P.; Garner, F. A. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/S0022-3115(03)00003-5	journal	April 2003
On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys Allen, T. R.; Busby, J. T.; Was, G. S. Journal of Nuclear Materials, Vol. 255, Issue 1 https://doi.org/10.1016/S0022-3115(98)00010-5	journal	May 1998
Radiation Damage in Austenitic Steels Garner, F. A. Comprehensive Nuclear Materials https://doi.org/10.1016/b978-0-08-056033-5.00065-3	book	January 2012
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy Hu, Rong; Smith, George D. W.; Marquis, Emmanuelle A. Acta Materialia, Vol. 61, Issue 9 https://doi.org/10.1016/j.actamat.2013.02.043	journal	May 2013
Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character Barr, Christopher M.; Vetterick, Gregory A.; Unocic, Kinga A. Acta Materialia, Vol. 67 https://doi.org/10.1016/j.actamat.2013.11.060	journal	April 2014
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments Field, Kevin G.; Yang, Ying; Allen, Todd R. Acta Materialia, Vol. 89 https://doi.org/10.1016/j.actamat.2015.01.064	journal	May 2015
Modified evolution equations for the precipitation kinetics of complex phases in multi-component systems Kozeschnik, E.; Svoboda, J.; Fischer, F. D. Calphad, Vol. 28, Issue 4 https://doi.org/10.1016/j.calphad.2004.11.003	journal	December 2004
Experimental investigation and thermodynamic modeling of the Mn–Ni–Si system Hu, Biao; Xu, Honghui; Liu, Shuhong Calphad, Vol. 35, Issue 3 https://doi.org/10.1016/j.calphad.2011.05.001	journal	September 2011
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure Pokor, C.; Brechet, Y.; Dubuisson, P. Journal of Nuclear Materials, Vol. 326, Issue 1 https://doi.org/10.1016/j.jnucmat.2003.11.007	journal	March 2004
Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70dpa Edwards, D. J.; Garner, F. A.; Bruemmer, S. M. Journal of Nuclear Materials, Vol. 384, Issue 3 https://doi.org/10.1016/j.jnucmat.2008.11.025	journal	February 2009
Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys Tucker, J. D.; Najafabadi, R.; Allen, T. R. Journal of Nuclear Materials, Vol. 405, Issue 3 https://doi.org/10.1016/j.jnucmat.2010.08.003	journal	October 2010
Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel Field, Kevin G.; Barnard, Leland M.; Parish, Chad M. Journal of Nuclear Materials, Vol. 435, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.026	journal	April 2013
Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe–21Cr–32Ni) Tan, L.; Busby, J. T.; Chichester, H. J. M. Journal of Nuclear Materials, Vol. 437, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.333	journal	June 2013
Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels Tan, L.; Busby, J. T. Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.054	journal	November 2013
Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316 Lee, Gyeong-Geun; Jin, Hyung-Ha; Lee, Yong-Bok Journal of Nuclear Materials, Vol. 449, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.049	journal	June 2014
Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9wt.% Cr model ferritic/martensitic steel Field, Kevin G.; Miller, Brandon D.; Chichester, Heather J. M. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.056	journal	February 2014
Strain-induced phase transformation at the surface of an AISI-304 stainless steel irradiated to 4.4dpa and deformed to 0.8% strain Gussev, M. N.; Field, K. G.; Busby, J. T. Journal of Nuclear Materials, Vol. 446, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.11.041	journal	March 2014
Magnetic phase formation in irradiated austenitic alloys Gussev, M. N.; Busby, J. T.; Tan, L. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.02.005	journal	May 2014
Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation Shim, Jae-Hyeok; Povoden-Karadeniz, Erwin; Kozeschnik, Ernst Journal of Nuclear Materials, Vol. 462 https://doi.org/10.1016/j.jnucmat.2015.04.013	journal	July 2015
Formulating the strength factor α for improved predictability of radiation hardening Tan, L.; Busby, J. T. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.07.009	journal	October 2015
Solute segregation on Σ3 and random grain boundaries in type 316L stainless steel Tomozawa, Masanari; Miyahara, Yuichi; Kako, Kenji Materials Science and Engineering: A, Vol. 578 https://doi.org/10.1016/j.msea.2013.04.048	journal	August 2013
Radiation-induced degradation of stainless steel light water reactor internals Kenik, Edward A.; Busby, Jeremy T. Materials Science and Engineering: R: Reports, Vol. 73, Issue 7-8 https://doi.org/10.1016/j.mser.2012.05.002	journal	July 2012
On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials Stoller, R. E.; Zinkle, S. J. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/s0022-3115(00)00378-0	journal	December 2000
Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels Duh, T. S.; Kai, J. J.; Chen, F. R. Journal of Nuclear Materials, Vol. 294, Issue 3 https://doi.org/10.1016/s0022-3115(01)00493-7	journal	April 2001
Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C Edwards, D. J.; Simonen, E. P.; Bruemmer, S. M. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/s0022-3115(03)00002-3	journal	April 2003
Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS Edwards, D. J.; Simonen, E. P.; Garner, F. A. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/s0022-3115(03)00003-5	journal	April 2003
On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys Allen, T. R.; Busby, J. T.; Was, G. S. Journal of Nuclear Materials, Vol. 255, Issue 1 https://doi.org/10.1016/s0022-3115(98)00010-5	journal	May 1998
Current understanding of radiation-induced degradation in light water reactor structural materials Fukuya, Koji Journal of Nuclear Science and Technology, Vol. 50, Issue 3 https://doi.org/10.1080/00223131.2013.772448	journal	March 2013
Grouping method for the approximate solution of a kinetic equation describing the evolution of point-defect clusters Golubov, S. I.; Ovcharenko, A. M.; Barashev, A. V. Philosophical Magazine A, Vol. 81, Issue 3 https://doi.org/10.1080/01418610108212164	journal	March 2001
Grouping method for the approximate solution of a kinetic equation describing the evolution of point-defect clusters I. Golubov, A. M. Ovcharenko, A. V., S. Philosophical Magazine A, Vol. 81, Issue 3 https://doi.org/10.1080/014186101300060928	journal	March 2001
The spatial resolution of X-ray microanalysis in the scanning transmission electron microscope Doig, P.; Lonsdale, D.; Flewitt, P. E. J. Philosophical Magazine A, Vol. 41, Issue 5 https://doi.org/10.1080/01418618008239347	journal	May 1980
Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation Fukuya, Koji; Fujii, Katsuhiko; Nishioka, Hiromasa Journal of Nuclear Science and Technology, Vol. 43, Issue 2 https://doi.org/10.1080/18811248.2006.9711078	journal	February 2006
Correlation of Yield Strength with Irradiation-Induced Microstructure in AISI Type 316 Stainless Steel Simons, Robert L.; Hulbert, Laura A. Effects of Radiation on Materials: 12th International Symposium Volume II https://doi.org/10.1520/STP87019850020	book	November 1985
Correlation of Yield Strength with Irradiation-Induced Microstructure in AISI Type 316 Stainless Steel Simons, Robert L.; Hulbert, Laura A. Effects of Radiation on Materials: 12th International Symposium Volume II https://doi.org/10.1520/stp87019850020	book	November 1985
Thermodynamic Analysis of the Ni-Si-Ti System Using Thermochemical Properties Determined from Ab Initio Calculations Tokunaga, Tatsuya; Hashima, Koji; Ohtani, Hiroshi MATERIALS TRANSACTIONS, Vol. 45, Issue 5 https://doi.org/10.2320/matertrans.45.1507	journal	January 2004

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