The role of nickel in radiation damage of ferritic alloys

Osetsky, Y.; Anento, Napoleon; Serra, Anna; Terentyev, D.

doi:10.1016/j.actamat.2014.10.060

Title: The role of nickel in radiation damage of ferritic alloys

Journal Article · Wed Nov 26 00:00:00 EST 2014 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2014.10.060· OSTI ID:1271881

Osetsky, Y. ^[1]; Anento, Napoleon ^[2]; Serra, Anna ^[2]; Terentyev, D. ^[3]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Polytechnic University of Catalonia, Barcelona (Spain)
Nuclear Materials Science Institute, Boeretang (Belgium)

According to modern theory, damage evolution under neutron irradiation depends on the fraction of self-interstitial atoms (SIAs) produced in the form of one-dimensional glissile clusters. These clusters, having a low interaction cross-section with other defects, are absorbed mainly by grain boundaries and dislocations, creating the so-called production bias. It is known empirically that the addition of certain alloying elements influences many radiation effects, including swelling; however, the mechanisms are unknown in many cases. In this study, we report the results of an extensive multi-technique atomistic level modeling study of SIA clusters mobility in body-centered cubic Fe–Ni alloys. We have found that Ni interacts strongly with the periphery of clusters, affecting their mobility. The total effect is defined by the number of Ni atoms interacting with the cluster at the same time and can be significant, even in low-Ni alloys. Thus a 1 nm (37SIAs) cluster is practically immobile at T < 500 K in the Fe–0.8 at.% Ni alloy. Increasing cluster size and Ni content enhances cluster immobilization. Finally, this effect should have quite broad consequences in void swelling, matrix damage accumulation and radiation induced hardening and the results obtained help to better understand and predict the effects of radiation in Fe–Ni ferritic alloys.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Energy Frontier Research Centers (EFRC) (United States). Center for Defect Physics in Structural Materials (CDP)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1271881

Alternate ID(s):: OSTI ID: 1250958

Journal Information:: Acta Materialia, Vol. 84; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 18 works

Citation information provided by
Web of Science

References (32)

Embrittlement of nuclear reactor pressure vessels Odette, G. R.; Lucas, G. E. JOM, Vol. 53, Issue 7 https://doi.org/10.1007/s11837-001-0081-0	journal	July 2001
The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals Dudarev, S. L.; Boutard, J. -L.; Lässer, R. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.301	journal	April 2009
Void formation in nickel during 20 MeV C++ irradiation at 525 °C Hudson, J. A.; Mazey, D. J.; Nelson, R. S. Journal of Nuclear Materials, Vol. 41, Issue 3 https://doi.org/10.1016/0022-3115(71)90163-2	journal	December 1971
The use of the high voltage electron microscope to simulate fast neutron-induced void swelling in metals Norris, D. I. R. Journal of Nuclear Materials, Vol. 40, Issue 1 https://doi.org/10.1016/0022-3115(71)90117-6	journal	July 1971
Void swelling and defect cluster formation in reactor-irradiated copper Zinkle, S. J.; Farrell, K. Journal of Nuclear Materials, Vol. 168, Issue 3 https://doi.org/10.1016/0022-3115(89)90591-6	journal	December 1989
On the origin of radiation growth of hcp crystals Golubov, Stanislav I.; Barashev, Aleksandr; Stoller, Roger E. https://doi.org/10.2172/1037031	report	March 2012
A proposed method of calculating displacement dose rates Norgett, M. J.; Robinson, M. T.; Torrens, I. M. Nuclear Engineering and Design, Vol. 33, Issue 1 https://doi.org/10.1016/0029-5493(75)90035-7	journal	August 1975
On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels Odette, G. R. Scripta Metallurgica, Vol. 17, Issue 10 https://doi.org/10.1016/0036-9748(83)90280-6	journal	October 1983
Effect of Copper and Nickel on the Neutron Irradiation Damage in Iron Alloys Hoelzer, D. T.; Ebrahimi, F. MRS Proceedings, Vol. 373 https://doi.org/10.1557/PROC-373-57	journal	January 1994
Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys Debarberis, L.; Acosta, B.; Sevini, F. Journal of Nuclear Materials, Vol. 336, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.10.002	journal	February 2005
Development of new interatomic potentials appropriate for crystalline and liquid iron Mendelev, M. I.; Han, S.; Srolovitz, D. J. Philosophical Magazine, Vol. 83, Issue 35 https://doi.org/10.1080/14786430310001613264	journal	December 2003
Fe–Ni many-body potential for metallurgical applications Bonny, G.; Pasianot, R. C.; Malerba, L. Modelling and Simulation in Materials Science and Engineering, Vol. 17, Issue 2 https://doi.org/10.1088/0965-0393/17/2/025010	journal	January 2009
Accurate Interatomic Potentials for Ni, Al and Ni3Al Voter, Arthur F.; Chen, Shao Ping MRS Proceedings, Vol. 82 https://doi.org/10.1557/PROC-82-175	journal	January 1986
Atomistic study of multimechanism diffusion by self-interstitial defects in α-Fe Anento, N.; Serra, A.; Osetsky, Yu N. Modelling and Simulation in Materials Science and Engineering, Vol. 18, Issue 2 https://doi.org/10.1088/0965-0393/18/2/025008	journal	January 2010
Modelling the diffusion of self-interstitial atom clusters in Fe-Cr alloys Terentyev, D.; Malerba, L.; Barashev, A. V. Philosophical Magazine, Vol. 88, Issue 1 https://doi.org/10.1080/14786430701727513	journal	January 2008
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
Primary damage formation in bcc iron Stoller, R. E.; Odette, G. R.; Wirth, B. D. Journal of Nuclear Materials, Vol. 251 https://doi.org/10.1016/S0022-3115(97)00256-0	journal	November 1997
Dependence of radiation damage accumulation in iron on underlying models of displacement cascades and subsequent defect migration Souidi, A.; Becquart, C. S.; Domain, C. Journal of Nuclear Materials, Vol. 355, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.04.009	journal	September 2006
Effect of mass of the primary knock-on atom on displacement cascade debris in α -iron Calder, A. F.; Bacon, D. J.; Barashev, A. V. Philosophical Magazine Letters, Vol. 88, Issue 1 https://doi.org/10.1080/09500830701733004	journal	January 2008
Structure and properties of clusters of self-interstitial atoms in fcc copper and bcc iron Osetsky, Yu. N.; Serra, A.; Singh, B. N. Philosophical Magazine A, Vol. 80, Issue 9 https://doi.org/10.1080/01418610008212155	journal	September 2000
Mechanism of one-dimensional glide of self-interstitial atom clusters in α-iron Barashev, A. V.; Osetsky, Yu. N.; Bacon, D. J. Philosophical Magazine A, Vol. 80, Issue 11 https://doi.org/10.1080/01418610008216500	journal	November 2000
One-dimensional atomic transport by clusters of self-interstitial atoms in iron and copper Osetsky, Yu. N.; Bacon, D. J.; Serra, A. Philosophical Magazine, Vol. 83, Issue 1 https://doi.org/10.1080/0141861021000016793	journal	January 2003
Radiation hardening revisited: role of intracascade clustering Singh, B. N.; Foreman, A. J. E.; Trinkaus, H. Journal of Nuclear Materials, Vol. 249, Issue 2-3 https://doi.org/10.1016/S0022-3115(97)00231-6	journal	October 1997
Analysis of displacement damage and defect production under cascade damage conditions Zinkle, S. J.; Singh, B. N. Journal of Nuclear Materials, Vol. 199, Issue 3 https://doi.org/10.1016/0022-3115(93)90140-T	journal	February 1993
Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions Trinkaus, H.; Singh, B. N.; Foreman, A. J. E. Journal of Nuclear Materials, Vol. 249, Issue 2-3 https://doi.org/10.1016/S0022-3115(97)00230-4	journal	October 1997
Solving the Puzzle of $⟨ 100 ⟩$ Interstitial Loop Formation in bcc Iron Xu, Haixuan; Stoller, Roger E.; Osetsky, Yury N. Physical Review Letters, Vol. 110, Issue 26 https://doi.org/10.1103/PhysRevLett.110.265503	journal	June 2013
Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys Terentyev, D.; Bergner, F.; Osetsky, Y. Acta Materialia, Vol. 61, Issue 5 https://doi.org/10.1016/j.actamat.2012.11.021	journal	March 2013
Vacancy interaction with glissile interstitial clusters in bcc metals Pelfort, M.; Osetsky, Yu. N.; Serra, A. Philosophical Magazine Letters, Vol. 81, Issue 12 https://doi.org/10.1080/09500830110095171	journal	December 2001
Interactions between vacancy and glissile interstitial clusters in iron and copper Puigvi, M. A.; Osetsky, Yu. N.; Serra, A. Materials Science and Engineering: A, Vol. 365, Issue 1-2 https://doi.org/10.1016/j.msea.2003.09.013	journal	January 2004
Development of numerical simulation tools in the Euratom Framework Programmes Hugon, M. Journal of Nuclear Materials, Vol. 406, Issue 1 https://doi.org/10.1016/j.jnucmat.2009.04.006	journal	November 2010
Transmission electron microscopy study on neutron irradiated pure iron and RPV model alloys Hernández-Mayoral, M.; Gómez-Briceño, D. Journal of Nuclear Materials, Vol. 399, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2009.11.013	journal	April 2010
Study of defect annealing behaviour in neutron irradiated Cu and Fe using positron annihilation and electrical conductivity Eldrup, M.; Singh, B. N. Journal of Nuclear Materials, Vol. 276, Issue 1-3 https://doi.org/10.1016/S0022-3115(99)00186-5	journal	January 2000

Similar Records

Radiation Effects in Innovative Structural Materials

Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1271881

Zinkle, S. J.; Ang, C. K.; Kiran Kumar, N. A.P.; +3 more

ATOMISTIC SIMULATION OF VACANCY AND SELF-INTERSTITIAL DIFFUSION IN Fe-Cu ALLOYS

Conference · Thu Jan 25 00:00:00 EST 2001 · OSTI ID:1271881

Marian, J; Wirth, B D; Perlado, J M; +1 more

Computer simulation of the effect of copper on defect production and damage evolution in ferritic steels

Conference · Sun Nov 28 00:00:00 EST 1999 · OSTI ID:1271881

Perlado, J M; Marian, J; Lodi, D

Related Subjects

36 MATERIALS SCIENCE
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
Dislocation loops
Fe–Ni alloys
Diffusion mechanism
Radiation effects

Title: The role of nickel in radiation damage of ferritic alloys

Citation Formats

References (32)

Similar Records

Related Subjects