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

Abstract

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 radiationmore » in Fe–Ni ferritic alloys.« less

Authors:

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)

Publication Date:: Wed Nov 26 00:00:00 EST 2014

Research Org.:: 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 Org.:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

OSTI Identifier:: 1271881

Alternate Identifier(s):: OSTI ID: 1250958

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Acta Materialia

Additional Journal Information:: Journal Volume: 84; Journal ID: ISSN 1359-6454

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

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

Citation Formats


                    Osetsky, Y., Anento, Napoleon, Serra, Anna, and Terentyev, D. The role of nickel in radiation damage of ferritic alloys.  United States: N. p., 2014. 
Web.  doi:10.1016/j.actamat.2014.10.060.

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                    Osetsky, Y., Anento, Napoleon, Serra, Anna, & Terentyev, D. The role of nickel in radiation damage of ferritic alloys.  United States.  https://doi.org/10.1016/j.actamat.2014.10.060

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                    Osetsky, Y., Anento, Napoleon, Serra, Anna, and Terentyev, D. Wed .  
"The role of nickel in radiation damage of ferritic alloys".  United States.  https://doi.org/10.1016/j.actamat.2014.10.060.  https://www.osti.gov/servlets/purl/1271881.

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@article{osti_1271881,

  title        = {The role of nickel in radiation damage of ferritic alloys},

  author       = {Osetsky, Y. and Anento, Napoleon and Serra, Anna and Terentyev, D.},

  abstractNote = {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.},

  doi          = {10.1016/j.actamat.2014.10.060},

  journal      = {Acta Materialia},

  number       = ,

  volume       = 84,

  place        = {United States},

  year         = {Wed Nov 26 00:00:00 EST 2014},

  month        = {Wed Nov 26 00:00:00 EST 2014}

}

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

Abstract

Citation Formats

Embrittlement of nuclear reactor pressure vessels journal, July 2001

The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals journal, April 2009

Void formation in nickel during 20 MeV C++ irradiation at 525 °C journal, December 1971

The use of the high voltage electron microscope to simulate fast neutron-induced void swelling in metals journal, July 1971

Void swelling and defect cluster formation in reactor-irradiated copper journal, December 1989

On the origin of radiation growth of hcp crystals report, March 2012

A proposed method of calculating displacement dose rates journal, August 1975

On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels journal, October 1983

Effect of Copper and Nickel on the Neutron Irradiation Damage in Iron Alloys journal, January 1994

Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys journal, February 2005

Development of new interatomic potentials appropriate for crystalline and liquid iron journal, December 2003

Fe–Ni many-body potential for metallurgical applications journal, January 2009

Accurate Interatomic Potentials for Ni, Al and Ni3Al journal, January 1986

Atomistic study of multimechanism diffusion by self-interstitial defects in α-Fe journal, January 2010

Modelling the diffusion of self-interstitial atom clusters in Fe-Cr alloys journal, January 2008

MD description of damage production in displacement cascades in copper and α-iron journal, December 2003

Primary damage formation in bcc iron journal, November 1997

Dependence of radiation damage accumulation in iron on underlying models of displacement cascades and subsequent defect migration journal, September 2006

Effect of mass of the primary knock-on atom on displacement cascade debris in α -iron journal, January 2008

Structure and properties of clusters of self-interstitial atoms in fcc copper and bcc iron journal, September 2000

Mechanism of one-dimensional glide of self-interstitial atom clusters in α-iron journal, November 2000

One-dimensional atomic transport by clusters of self-interstitial atoms in iron and copper journal, January 2003

Radiation hardening revisited: role of intracascade clustering journal, October 1997

Analysis of displacement damage and defect production under cascade damage conditions journal, February 1993

Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions journal, October 1997

Solving the Puzzle of ⟨ 100 ⟩ Interstitial Loop Formation in bcc Iron journal, June 2013

Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys journal, March 2013

Vacancy interaction with glissile interstitial clusters in bcc metals journal, December 2001

Interactions between vacancy and glissile interstitial clusters in iron and copper journal, January 2004

Development of numerical simulation tools in the Euratom Framework Programmes journal, November 2010

Transmission electron microscopy study on neutron irradiated pure iron and RPV model alloys journal, April 2010

Study of defect annealing behaviour in neutron irradiated Cu and Fe using positron annihilation and electrical conductivity journal, January 2000

Embrittlement of nuclear reactor pressure vessels
journal, July 2001

The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals
journal, April 2009

Void formation in nickel during 20 MeV C++ irradiation at 525 °C
journal, December 1971

The use of the high voltage electron microscope to simulate fast neutron-induced void swelling in metals
journal, July 1971

Void swelling and defect cluster formation in reactor-irradiated copper
journal, December 1989

On the origin of radiation growth of hcp crystals
report, March 2012

A proposed method of calculating displacement dose rates
journal, August 1975

On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels
journal, October 1983

Effect of Copper and Nickel on the Neutron Irradiation Damage in Iron Alloys
journal, January 1994

Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys
journal, February 2005

Development of new interatomic potentials appropriate for crystalline and liquid iron
journal, December 2003

Fe–Ni many-body potential for metallurgical applications
journal, January 2009

Accurate Interatomic Potentials for Ni, Al and Ni3Al
journal, January 1986

Atomistic study of multimechanism diffusion by self-interstitial defects in α-Fe
journal, January 2010

Modelling the diffusion of self-interstitial atom clusters in Fe-Cr alloys
journal, January 2008

MD description of damage production in displacement cascades in copper and α-iron
journal, December 2003

Primary damage formation in bcc iron
journal, November 1997

Dependence of radiation damage accumulation in iron on underlying models of displacement cascades and subsequent defect migration
journal, September 2006

Effect of mass of the primary knock-on atom on displacement cascade debris in α -iron
journal, January 2008

Structure and properties of clusters of self-interstitial atoms in fcc copper and bcc iron
journal, September 2000

Mechanism of one-dimensional glide of self-interstitial atom clusters in α-iron
journal, November 2000

One-dimensional atomic transport by clusters of self-interstitial atoms in iron and copper
journal, January 2003

Radiation hardening revisited: role of intracascade clustering
journal, October 1997

Analysis of displacement damage and defect production under cascade damage conditions
journal, February 1993

Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions
journal, October 1997

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Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys
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