Mechanism-based modeling of thermal and irradiation creep behavior: An application to ferritic/martensitic HT9 steel

Wen, Wei; Kohnert, Aaron Anthony; Kumar, M. Arul; Capolungo, Laurent; Tomé, Carlos N.

doi:10.1016/j.ijplas.2019.11.012

Title: Mechanism-based modeling of thermal and irradiation creep behavior: An application to ferritic/martensitic HT9 steel

Journal Article · 28 November 2019 · International Journal of Plasticity

DOI: https://doi.org/10.1016/j.ijplas.2019.11.012 · OSTI ID:1581575

Wen, Wei ^[1]; Kohnert, Aaron Anthony ^[2];

^[2];

^[2]; Tomé, Carlos N. ^[2]

Lancaster Univ., Lancaster (United Kingdom)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

In this work, the creep behavior of HT9 steel in both thermal and irradiation environments is predicted using an integrated modeling framework. Multiple physical mechanisms such as diffusional creep and dislocation climb are incorporated into crystal plasticity calculations using the Visco-Plastic Self-Consistent (VPSC) approach. Climb velocities are informed by mean field rate theory laws in place of empirical power law formulations. More interestingly, the climb velocities explicitly consider the contribution of irradiation-induced point defects, i.e., stress induced preferential absorption (SIPA) effect. The developed expressions are shown to apply under conventional thermal creep and to the more complex irradiation conditions as well. This physically-informed, mechanism-based model is used to simulate the creep strain evolution of HT9 pressurized tubes under various loading conditions. Furthermore, it is demonstrated that the experimental behavior of this material reported in the literature is well described by this theoretical framework. The role of each relevant mechanism is discussed.

View Accepted Manuscript (DOE)

Cite

Export

Save

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

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: 89233218CNA000001

OSTI ID:: 1581575

Report Number(s):: LA-UR--19-28064

Journal Information:: International Journal of Plasticity, Journal Name: International Journal of Plasticity Journal Issue: C Vol. 126; ISSN 0749-6419

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (51)

The determination of density and distribution of dislocations in deformed single crystals from broadened X-ray diffraction profiles Wilkens, M. Physica Status Solidi (a), Vol. 2, Issue 2 https://doi.org/10.1002/pssa.19700020224	journal	June 1970
A Statistical Theory of Solid Solution Hardening Labusch, R. physica status solidi (b), Vol. 41, Issue 2 https://doi.org/10.1002/pssb.19700410221	journal	January 1970
Scaling of Dislocation Strengthening by Multiple Obstacle Types Dong, Y.; Nogaret, T.; Curtin, W. A. Metallurgical and Materials Transactions A, Vol. 41, Issue 8 https://doi.org/10.1007/s11661-010-0229-z	journal	June 2010
Analysis of Obstacle Hardening Models Using Dislocation Dynamics: Application to Irradiation-Induced Defects Sobie, Cameron; Bertin, Nicolas; Capolungo, Laurent Metallurgical and Materials Transactions A, Vol. 46, Issue 8 https://doi.org/10.1007/s11661-015-2935-z	journal	May 2015
A Physics-Based Crystallographic Modeling Framework for Describing the Thermal Creep Behavior of Fe-Cr Alloys Wen, W.; Capolungo, L.; Patra, A. Metallurgical and Materials Transactions A, Vol. 48, Issue 5 https://doi.org/10.1007/s11661-017-4011-3	journal	February 2017
Multislip in f.c.c. crystals a theoretical approach compared with experimental data Franciosi, P.; Zaoui, A. Acta Metallurgica, Vol. 30, Issue 8 https://doi.org/10.1016/0001-6160(82)90184-5	journal	August 1982
Irradiation creep and interrelation with swelling in austenitic stainless steels Ehrlich, Karl Journal of Nuclear Materials, Vol. 100, Issue 1-3 https://doi.org/10.1016/0022-3115(81)90531-6	journal	September 1981
Irradiation creep due to elastodiffusion Woo, C. H. Journal of Nuclear Materials, Vol. 120, Issue 1 https://doi.org/10.1016/0022-3115(84)90170-3	journal	February 1984
Irradiation creep models — an overview Matthews, J. R.; Finnis, M. W. Journal of Nuclear Materials, Vol. 159 https://doi.org/10.1016/0022-3115(88)90097-9	journal	October 1988
Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix Dubuisson, P.; Gilbon, D.; Séran, J. L. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90080-I	journal	October 1993
Microstructural analysis of neutron-irradiated martensitic steels Kai, J. J.; Klueh, R. L. Journal of Nuclear Materials, Vol. 230, Issue 2 https://doi.org/10.1016/0022-3115(96)00165-1	journal	June 1996
A self-consistent anisotropic approach for the simulation of plastic deformation and texture development of polycrystals: Application to zirconium alloys Lebensohn, R. A.; Tomé, C. N. Acta Metallurgica et Materialia, Vol. 41, Issue 9 https://doi.org/10.1016/0956-7151(93)90130-K	journal	September 1993
Irradiation creep of 11Cr–0.5Mo–2W,V,Nb ferritic–martensitic, modified 316, and 15Cr–20Ni austenitic S.S. irradiated in FFTF to 103–206 dpa Uehira, A.; Mizuta, S.; Ukai, S. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00079-9	journal	December 2000
Dislocation theory based constitutive modelling: foundations and applications Estrin, Y. Journal of Materials Processing Technology, Vol. 80-81 https://doi.org/10.1016/S0924-0136(98)00208-8	journal	August 1998
Double strengthening of copper by dissolved gold-atoms and by incoherent SiO2-particles: how do the two strengthening contributions superimpose? Lagerpusch, U.; Mohles, V.; Baither, D. Acta Materialia, Vol. 48, Issue 14 https://doi.org/10.1016/S1359-6454(00)00172-5	journal	September 2000
A mechanism for the negative strain-rate sensitivity of dilute solid solutions Picu, R. C. Acta Materialia, Vol. 52, Issue 12 https://doi.org/10.1016/j.actamat.2004.03.042	journal	July 2004
Solute strengthening of both mobile and forest dislocations: The origin of dynamic strain aging in fcc metals Soare, M. A.; Curtin, W. A. Acta Materialia, Vol. 56, Issue 15 https://doi.org/10.1016/j.actamat.2008.04.027	journal	September 2008
Single-mechanism rate theory for dynamic strain aging in fcc metals Soare, M. A.; Curtin, W. A. Acta Materialia, Vol. 56, Issue 15 https://doi.org/10.1016/j.actamat.2008.04.030	journal	September 2008
Mechanical behavior of low carbon steel subjected to strain path changes: Experiments and modeling Wen, W.; Borodachenkova, M.; Tomé, C. N. Acta Materialia, Vol. 111 https://doi.org/10.1016/j.actamat.2016.03.075	journal	June 2016
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C. Acta Materialia, Vol. 129 https://doi.org/10.1016/j.actamat.2017.02.077	journal	May 2017
A dislocation-based constitutive model for viscoplastic deformation of fcc metals at very high strain rates Austin, Ryan A.; McDowell, David L. International Journal of Plasticity, Vol. 27, Issue 1 https://doi.org/10.1016/j.ijplas.2010.03.002	journal	January 2011
A crystallographic dislocation model for describing hardening of polycrystals during strain path changes. Application to low carbon steels Kitayama, K.; Tomé, C. N.; Rauch, E. F. International Journal of Plasticity, Vol. 46 https://doi.org/10.1016/j.ijplas.2012.09.004	journal	July 2013
Stress and strain relaxation in magnesium AZ31 rolled plate: In-situ neutron measurement and elastic viscoplastic polycrystal modeling Wang, H.; Clausen, B.; Capolungo, L. International Journal of Plasticity, Vol. 79 https://doi.org/10.1016/j.ijplas.2015.07.004	journal	April 2016
A crystal plasticity model based on transition state theory Wang, H.; Capolungo, L.; Clausen, B. International Journal of Plasticity, Vol. 93 https://doi.org/10.1016/j.ijplas.2016.05.003	journal	June 2017
Mechanism-based modeling of solute strengthening: Application to thermal creep in Zr alloy Wen, Wei; Capolungo, Laurent; Tomé, Carlos N. International Journal of Plasticity, Vol. 106 https://doi.org/10.1016/j.ijplas.2018.03.003	journal	July 2018
Plane wave simulation of elastic-viscoplastic single crystals Lloyd, J. T.; Clayton, J. D.; Austin, R. A. Journal of the Mechanics and Physics of Solids, Vol. 69 https://doi.org/10.1016/j.jmps.2014.04.009	journal	September 2014
MD description of damage production in displacement cascades in copper and α-iron Bacon, D. J.; Osetsky, Yu. N.; Stoller, R. Journal of Nuclear Materials, Vol. 323, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2003.08.002	journal	December 2003
Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C Sencer, B. H.; Kennedy, J. R.; Cole, J. I. Journal of Nuclear Materials, Vol. 393, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.06.010	journal	September 2009
Phase stability of an HT-9 duct irradiated in FFTF Anderoglu, O.; Van den Bosch, J.; Hosemann, P. Journal of Nuclear Materials, Vol. 430, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.06.038	journal	November 2012
Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys Chen, Wei-Ying; Miao, Yinbin; Wu, Yaqiao Journal of Nuclear Materials, Vol. 462 https://doi.org/10.1016/j.jnucmat.2015.04.005	journal	July 2015
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.023	journal	October 2015
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 Maloy, S. A.; Saleh, T. A.; Anderoglu, O. Journal of Nuclear Materials, Vol. 468 https://doi.org/10.1016/j.jnucmat.2015.07.039	journal	January 2016
The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels Getto, E.; Vancoevering, G.; Was, G. S. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.12.006	journal	February 2017
Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel Zheng, Ce; Auger, Maria A.; Moody, Michael P. Journal of Nuclear Materials, Vol. 491 https://doi.org/10.1016/j.jnucmat.2017.04.040	journal	August 2017
Irradiation-enhanced α′ precipitation in model FeCrAl alloys Edmondson, P. D.; Briggs, S. A. Scripta Materialia, Vol. 116 https://doi.org/10.1016/j.scriptamat.2016.02.002	journal	April 2016
A Model for Boundary Diffusion Controlled Creep in Polycrystalline Materials Coble, R. L. Journal of Applied Physics, Vol. 34, Issue 6 https://doi.org/10.1063/1.1702656	journal	June 1963
Entropy Factors for Thermally Activated Unpinning of Dislocations Granato, A. V.; Lücke, K.; Schlipf, J. Journal of Applied Physics, Vol. 35, Issue 9 https://doi.org/10.1063/1.1713833	journal	September 1964
Dislocation motion in a random solid solution Zaiser, Michael Philosophical Magazine A, Vol. 82, Issue 15 https://doi.org/10.1080/01418610208240071	journal	October 2002
Self-consistent modelling of the mechanical behaviour of viscoplastic polycrystals incorporating intragranular field fluctuations Lebensohn, R. A.; Tomé, C. N.; CastaÑeda, P. Ponte Philosophical Magazine, Vol. 87, Issue 28 https://doi.org/10.1080/14786430701432619	journal	August 2007
Modeling the mechanical response of polycrystals deforming by climb and glide Lebensohn, Ricardo A.; Hartley, Craig S.; Tomé, Carlos N. Philosophical Magazine, Vol. 90, Issue 5 https://doi.org/10.1080/14786430903213320	journal	February 2010
Steady-state irradiation creep Heald, P. T.; Speight, M. V. Philosophical Magazine, Vol. 29, Issue 5 https://doi.org/10.1080/14786437408226592	journal	May 1974
The stress-induced point defect-dislocation interaction and its relevance to irradiation creep Bullough, R.; Willis, J. R. Philosophical Magazine, Vol. 31, Issue 4 https://doi.org/10.1080/14786437508229635	journal	April 1975
Cascade morphology transition in bcc metals Setyawan, Wahyu; Selby, Aaron P.; Juslin, Niklas Journal of Physics: Condensed Matter, Vol. 27, Issue 22 https://doi.org/10.1088/0953-8984/27/22/225402	journal	May 2015
Solute strengthening at high temperatures Leyson, G. P. M.; Curtin, W. A. Modelling and Simulation in Materials Science and Engineering, Vol. 24, Issue 6 https://doi.org/10.1088/0965-0393/24/6/065005	journal	July 2016
Precipitate design for creep strengthening of 9% Cr tempered martensitic steel for ultra-supercritical power plants Abe, Fujio Science and Technology of Advanced Materials, Vol. 9, Issue 1 https://doi.org/10.1088/1468-6996/9/1/013002	journal	January 2008
Probability distribution of internal stresses in parallel straight dislocation systems Groma, I.; Bakó, B. Physical Review B, Vol. 58, Issue 6 https://doi.org/10.1103/PhysRevB.58.2969	journal	August 1998
Molecular dynamics study of self-diffusion in bcc Fe Mendelev, Mikhail I.; Mishin, Yuri Physical Review B, Vol. 80, Issue 14 https://doi.org/10.1103/PhysRevB.80.144111	journal	October 2009
Free Energy Generalization of the Peierls Potential in Iron Gilbert, M. R.; Schuck, P.; Sadigh, B. Physical Review Letters, Vol. 111, Issue 9 https://doi.org/10.1103/PhysRevLett.111.095502	journal	August 2013
Analysis of the asymptotic properties of X-ray line broadening caused by dislocations Groma, I.; Székely, F. Journal of Applied Crystallography, Vol. 33, Issue 6 https://doi.org/10.1107/S002188980001058X	journal	December 2000
Kinetics of α’-phase nucleation during thermal aging of Fe–22% Cr alloy Rogozhkin, S. V.; Korchuganova, O. A.; Aleev, A. A. Inorganic Materials: Applied Research, Vol. 7, Issue 2 https://doi.org/10.1134/S2075113316020179	journal	March 2016
Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors Klueh, R. L. International Materials Reviews, Vol. 50, Issue 5 https://doi.org/10.1179/174328005X41140	journal	October 2005

Similar Records

A physics-based crystallographic modeling framework for describing the thermal creep behavior of Fe-Cr alloys

Journal Article · 2017 · Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science · OSTI ID:1369190

Wen, Wei; Capolungo, Laurent; Patra, Anirban; +1 more

Irradiation Creep in Materials

Book · 2020 · OSTI ID:1657983

Onimus, Fabien; Jourdan, Thomas; Xu, Cheng; +2 more

Irradiation creep in simple binary alloys

Conference · 1981 · OSTI ID:6481631

Nagakawa, J; Sethi, V K; Turner, A P.L.

Related Subjects

36 MATERIALS SCIENCE
Crystal plasticity
HT9 steel
Irradiation creep
Thermal creep

Title: Mechanism-based modeling of thermal and irradiation creep behavior: An application to ferritic/martensitic HT9 steel

Citation Formats

References (51)

Similar Records

Related Subjects