The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys

Lin, Yan-Ru; Bhattacharya, Arunodaya; Zinkle, Steven J.

doi:10.1016/j.jnucmat.2022.153907

Title: The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys

Abstract

We report Ferritic-martensitic (FM) steels for in-vessel components in proposed fusion reactors are expected to suffer from high levels of displacement damage and helium (He) generation by neutron transmutation. However, a thorough understanding of the He synergistic effects on the cavity swelling in FM steels is still not well established. To gain fundamental insights into the He effect on cavity swelling, high purity Fe and Fe-10 wt.% Cr ferritic model alloys were irradiated with 8 MeV Ni ions and co-implanted He ions at 400 to 550 °C up to 30 displacements per atom (dpa) with He implantation rates of 0.1, 10 and 50 appm He/dpa. The current study focuses on the 50 appm He/dpa, 500 °C behavior vs. 0.1 and 10 appm He/dpa. Irradiation-induced defects, including cavities, dislocation loops, and dislocation networks were characterized using transmission electron microscopy (TEM). In the grain interior, a bimodal cavity size distribution was observed in the 10 and 50 appm He/dpa samples, but not for 0.1 appm He/dpa. Cavity swelling was maximized at intermediate He implantation rates of ~10 appm He/dpa for both ion-irradiated Fe and Fe-10Cr alloys. The cavity swelling behavior as a function of He implantation rate appears to be controlled bymore »« less

Authors:

^[1];

^[2]; Zinkle, Steven J. ^[1]

University of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Fri Jul 08 00:00:00 EDT 2022

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

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); Euratom Research and Training Program; State of Tennessee; Tennessee Higher Education Commission (THEC)

OSTI Identifier:: 1876306

Grant/Contract Number:: AC05-00OR22725; SC0006661; 633053

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 569; Journal Issue: n/a; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; helium effects; radiation damage; ferritic alloy; cavity swelling; transmission electron microscopy

Citation Formats


                    Lin, Yan-Ru, Bhattacharya, Arunodaya, and Zinkle, Steven J. The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys.  United States: N. p., 2022. 
Web.  doi:10.1016/j.jnucmat.2022.153907.

Copy to clipboard


                    Lin, Yan-Ru, Bhattacharya, Arunodaya, & Zinkle, Steven J. The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys.  United States.  https://doi.org/10.1016/j.jnucmat.2022.153907

Copy to clipboard


                    Lin, Yan-Ru, Bhattacharya, Arunodaya, and Zinkle, Steven J. Fri .  
"The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys".  United States.  https://doi.org/10.1016/j.jnucmat.2022.153907.  https://www.osti.gov/servlets/purl/1876306.

Copy to clipboard


                    
@article{osti_1876306,

  title        = {The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys},

  author       = {Lin, Yan-Ru and Bhattacharya, Arunodaya and Zinkle, Steven J.},

  abstractNote = {We report Ferritic-martensitic (FM) steels for in-vessel components in proposed fusion reactors are expected to suffer from high levels of displacement damage and helium (He) generation by neutron transmutation. However, a thorough understanding of the He synergistic effects on the cavity swelling in FM steels is still not well established. To gain fundamental insights into the He effect on cavity swelling, high purity Fe and Fe-10 wt.% Cr ferritic model alloys were irradiated with 8 MeV Ni ions and co-implanted He ions at 400 to 550 °C up to 30 displacements per atom (dpa) with He implantation rates of 0.1, 10 and 50 appm He/dpa. The current study focuses on the 50 appm He/dpa, 500 °C behavior vs. 0.1 and 10 appm He/dpa. Irradiation-induced defects, including cavities, dislocation loops, and dislocation networks were characterized using transmission electron microscopy (TEM). In the grain interior, a bimodal cavity size distribution was observed in the 10 and 50 appm He/dpa samples, but not for 0.1 appm He/dpa. Cavity swelling was maximized at intermediate He implantation rates of ~10 appm He/dpa for both ion-irradiated Fe and Fe-10Cr alloys. The cavity swelling behavior as a function of He implantation rate appears to be controlled by the He/dpa-dependent variation of cavity sink strengths. Treating small bubbles as biased sinks for interstitial absorption can significantly increase the ratio of biased to unbiased sink strengths (Q) and results in maximized cavity swelling for a Q ratio close to one.},

  doi          = {10.1016/j.jnucmat.2022.153907},

  journal      = {Journal of Nuclear Materials},

  number       = n/a,

  volume       = 569,

  place        = {United States},

  year         = {Fri Jul 08 00:00:00 EDT 2022},

  month        = {Fri Jul 08 00:00:00 EDT 2022}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.jnucmat.2022.153907

Other availability

Search WorldCat to find libraries that may hold this journal

Save / Share:

Export Metadata

Save to My Library

Works referenced in this record:

Materials challenges in nuclear energy
journal, February 2013

Zinkle, S. J.; Was, G. S.
Acta Materialia, Vol. 61, Issue 3
DOI: 10.1016/j.actamat.2012.11.004

On the origin of primary ½ a0 <111> and a0 <100> loops in irradiated Fe(Cr) alloys
journal, July 2017

Schäublin, R.; Décamps, B.; Prokhodtseva, A.
Acta Materialia, Vol. 133
DOI: 10.1016/j.actamat.2017.02.041

Fissile core and Tritium-Breeding Blanket: structural materials and their requirements
journal, April 2008

Boutard, Jean-Louis; Alamo, Ana; Lindau, Rainer
Comptes Rendus Physique, Vol. 9, Issue 3-4
DOI: 10.1016/j.crhy.2007.11.004

Atomic Configuration of Point Defect Clusters in Ion-Irradiated Silicon Carbide
journal, November 2017

Lin, Y. R.; Chen, L. G.; Hsieh, C. Y.
Scientific Reports, Vol. 7, Issue 1
DOI: 10.1038/s41598-017-15037-w

The influence of helium on cavity evolution in ion-irradiated T91
journal, October 2018

Monterrosa, Anthony M.; Jiao, Zhijie; Was, Gary S.
Journal of Nuclear Materials, Vol. 509
DOI: 10.1016/j.jnucmat.2018.06.033

Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys
journal, November 2020

Tan, L.; Graening, T.; Hu, X.
Journal of Nuclear Materials, Vol. 540
DOI: 10.1016/j.jnucmat.2020.152376

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys
journal, April 2021

Lin, Yan-Ru; Bhattacharya, Arunodaya; Chen, Da
Acta Materialia, Vol. 207
DOI: 10.1016/j.actamat.2021.116660

Critical radius for bias-driven swelling — a further analysis and its application to bimodal cavity size distributions
journal, August 1983

Hishinuma, A.; Mansur, L. K.
Journal of Nuclear Materials, Vol. 118, Issue 1
DOI: 10.1016/0022-3115(83)90184-8

Experimental effects of helium on cavity formation during irradiation—a review
journal, January 1980

Farrell, K.
Radiation Effects, Vol. 53, Issue 3-4
DOI: 10.1080/00337578008207114

Helium and point defect accumulation: (i) microstructure and mechanical behaviour
journal, April 2008

Schäublin, Robin; Henry, Jean; Dai, Yong
Comptes Rendus Physique, Vol. 9, Issue 3-4
DOI: 10.1016/j.crhy.2008.01.003

Mechanisms of helium interaction with radiation effects in metals and alloys: A review
journal, November 1983

Mansur, L. K.; Coghlan, W. A.
Journal of Nuclear Materials, Vol. 119, Issue 1
DOI: 10.1016/0022-3115(83)90047-8

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation
journal, August 2012

Gilbert, M. R.; Dudarev, S. L.; Zheng, S.
Nuclear Fusion, Vol. 52, Issue 8
DOI: 10.1088/0029-5515/52/8/083019

Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300°C and 400°C
journal, December 2000

Klueh, R. L.; Sokolov, M. A.; Shiba, K.
Journal of Nuclear Materials, Vol. 283-287
DOI: 10.1016/S0022-3115(00)00086-6

Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys
journal, December 2021

Bhattacharya, Arunodaya; Henry, Jean; Décamps, Brigitte
Journal of Nuclear Materials, Vol. 556
DOI: 10.1016/j.jnucmat.2021.153213

Microstructural evolution in dual-ion irradiated 316ss under various helium injection schedules
journal, May 1984

Kohyama, Akira; Ayrault, Guy; Igata, Naohiro
Journal of Nuclear Materials, Vol. 122, Issue 1-3
DOI: 10.1016/0022-3115(84)90600-7

Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic/martensitic alloys
journal, April 1990

Lee, E. H.; Mansur, L. K.
Metallurgical Transactions A, Vol. 21, Issue 4
DOI: 10.1007/BF02656524

Simulation irradiation studies on iron
journal, January 1981

Kuramoto, Eiichi; Yoshida, Naoaki; Tsukuda, Noboru
Journal of Nuclear Materials, Vol. 104
DOI: 10.1016/0022-3115(82)90746-2

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017

Zinkle, S. J.; Boutard, J. L.; Hoelzer, D. T.
Nuclear Fusion, Vol. 57, Issue 9
DOI: 10.1088/1741-4326/57/9/092005

Neutronics aspects of the FESS-FNSF
journal, October 2018

Davis, A.; Harb, M.; El-Guebaly, L.
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.06.008

Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
journal, August 1978

Mansur, L. K.
Nuclear Technology, Vol. 40, Issue 1
DOI: 10.13182/NT78-2

Formulation of voids and bubbles as biased sinks to crystalline point defects
journal, May 2021

Luo, Jing; Xin, Yong; Sun, Zhipeng
Scripta Materialia, Vol. 197
DOI: 10.1016/j.scriptamat.2021.113806

He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40wt.% Cr: A transmission electron microscopy study
journal, August 2013

Brimbal, Daniel; Meslin, Estelle; Henry, Jean
Acta Materialia, Vol. 61, Issue 13
DOI: 10.1016/j.actamat.2013.04.070

Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation
journal, May 2018

Chen, J.; Duval, F.; Jung, P.
Journal of Nuclear Materials, Vol. 503
DOI: 10.1016/j.jnucmat.2018.02.042

The effect of radiation upon diffusion in metals
journal, February 1978

Sizmann, Rudolf
Journal of Nuclear Materials, Vol. 69-70
DOI: 10.1016/0022-3115(78)90256-8

Analytical solutions for helium bubble and critical radius parameters using a hard sphere equation of state
journal, April 1985

Stoller, R. E.; Odette, G. R.
Journal of Nuclear Materials, Vol. 131, Issue 2-3
DOI: 10.1016/0022-3115(85)90450-7

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
journal, October 2020

Taller, Stephen; Was, Gary S.
Acta Materialia, Vol. 198
DOI: 10.1016/j.actamat.2020.07.060

On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science
journal, January 2018

Odette, G. Robert
Scripta Materialia, Vol. 143
DOI: 10.1016/j.scriptamat.2017.06.021

The Role of Co-injected Helium on Swelling and Cavity Evolution at High Damage Levels in Ferritic-Martensitic Steels
journal, July 2021

Woodley, D.; Taller, S.; Jiao, Z.
Journal of Nuclear Materials, Vol. 550
DOI: 10.1016/j.jnucmat.2021.152912

14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation
journal, December 1990

Kai, J. J.; Kulcinski, G. L.
Journal of Nuclear Materials, Vol. 175, Issue 3
DOI: 10.1016/0022-3115(90)90211-5

55Fe effect on enhancing ferritic steel He/dpa ratio in fission reactor irradiations to simulate fusion conditions
journal, November 2013

Liu, Haibo; Abdou, Mohamed A.; Greenwood, Larry R.
Fusion Engineering and Design, Vol. 88, Issue 11
DOI: 10.1016/j.fusengdes.2013.05.067

Molecular statics calculations of the biases and point defect capture volumes of small cavities
journal, February 2018

Kohnert, Aaron A.; Cusentino, Mary Alice; Wirth, Brian D.
Journal of Nuclear Materials, Vol. 499
DOI: 10.1016/j.jnucmat.2017.12.005

Atomic configuration of irradiation-induced planar defects in 3C-SiC
journal, March 2014

Lin, Y. R.; Ho, C. Y.; Hsieh, C. Y.
Applied Physics Letters, Vol. 104, Issue 12
DOI: 10.1063/1.4869829

Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys
journal, October 2013

Prokhodtseva, A.; Décamps, B.; Ramar, A.
Acta Materialia, Vol. 61, Issue 18
DOI: 10.1016/j.actamat.2013.08.007

Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications
journal, November 2014

Odette, G. R.
JOM, Vol. 66, Issue 12
DOI: 10.1007/s11837-014-1207-5

A dual ion irradiation study of helium–dpa interactions on cavity evolution in tempered martensitic steels and nanostructured ferritic alloys
journal, June 2014

Yamamoto, Takuya; Wu, Yuan; Robert Odette, G.
Journal of Nuclear Materials, Vol. 449, Issue 1-3
DOI: 10.1016/j.jnucmat.2014.01.040

Radiation and helium effects on microstructures, nano-indentation properties and deformation behavior in ferrous alloys
journal, December 2003

Katoh, Y.; Ando, M.; Kohyama, A.
Journal of Nuclear Materials, Vol. 323, Issue 2-3
DOI: 10.1016/j.jnucmat.2003.08.007

Dramatic reduction of void swelling by helium in ion-irradiated high purity α -iron
journal, April 2018

Bhattacharya, Arunodaya; Meslin, Estelle; Henry, Jean
Materials Research Letters, Vol. 6, Issue 7
DOI: 10.1080/21663831.2018.1462266

Helium accumulation in metals during irradiation – where do we stand?
journal, December 2003

Trinkaus, H.; Singh, B. N.
Journal of Nuclear Materials, Vol. 323, Issue 2-3
DOI: 10.1016/j.jnucmat.2003.09.001

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors
journal, December 2003

Baluc, N.; Schäublin, R.; Spätig, P.
Nuclear Fusion, Vol. 44, Issue 1
DOI: 10.1088/0029-5515/44/1/006

Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injection
journal, February 2014

Brimbal, Daniel; Décamps, Brigitte; Henry, Jean
Acta Materialia, Vol. 64
DOI: 10.1016/j.actamat.2013.10.052

Simulation of first wall damage: Effects of the method of gas implantation
journal, December 1979

Packan, N. H.; Farrell, K.
Journal of Nuclear Materials, Vol. 85-86
DOI: 10.1016/0022-3115(79)90338-6

Multiscale modelling of defect kinetics in irradiated iron
journal, December 2004

Fu, Chu-Chun; Torre, Jacques Dalla; Willaime, François
Nature Materials, Vol. 4, Issue 1
DOI: 10.1038/nmat1286

Cavity growth mechanism maps
journal, October 1984

Goodhew, P. J.
Scripta Metallurgica, Vol. 18, Issue 10
DOI: 10.1016/0036-9748(84)90180-7

Predicting structural material degradation in advanced nuclear reactors with ion irradiation
journal, February 2021

Taller, Stephen; VanCoevering, Gerrit; Wirth, Brian D.
Scientific Reports, Vol. 11, Issue 1
DOI: 10.1038/s41598-021-82512-w

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
journal, July 2015

Getto, E.; Jiao, Z.; Monterrosa, A. M.
Journal of Nuclear Materials, Vol. 462
DOI: 10.1016/j.jnucmat.2015.01.045

II. Effect of oxygen and helium on void formation in metals
journal, January 1987

Zinkle, S. J.; Wolfer, W. G.; Kulcinski, G. L.
Philosophical Magazine A, Vol. 55, Issue 1
DOI: 10.1080/01418618708209804

Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C
journal, May 2021

Lin, Yan-Ru; Chen, Wei-Ying; Li, Meimei
Acta Materialia, Vol. 209
DOI: 10.1016/j.actamat.2021.116793

The effect of stress on the microstructure of neutron irradiated cold worked type 316 stainless steel
journal, January 1974

Brager, H. R.; Gilbert, E. R.; Straalsund, J. L.
Radiation Effects, Vol. 21, Issue 1
DOI: 10.1080/10420157408230810

Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures
journal, September 2021

Lin, Yan-Ru; Chen, Wei-Ying; Tan, Lizhen
Acta Materialia, Vol. 217
DOI: 10.1016/j.actamat.2021.117165

Comparison between bulk and thin foil ion irradiation of ultra high purity Fe
journal, November 2013

Prokhodtseva, A.; Décamps, B.; Schäublin, R.
Journal of Nuclear Materials, Vol. 442, Issue 1-3
DOI: 10.1016/j.jnucmat.2013.04.032

Materials for future nuclear energy systems
journal, December 2019

Was, G. S.; Petti, D.; Ukai, S.
Journal of Nuclear Materials, Vol. 527
DOI: 10.1016/j.jnucmat.2019.151837

Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014

Zinkle, S. J.; Snead, L. L.
Annual Review of Materials Research, Vol. 44, Issue 1
DOI: 10.1146/annurev-matsci-070813-113627

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015

Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C.
Journal of Nuclear Materials, Vol. 465
DOI: 10.1016/j.jnucmat.2015.06.023

Effect of saddle point anisotropy of point defects on their absorption by dislocations and cavities
journal, September 2017

Carpentier, D.; Jourdan, T.; Le Bouar, Y.
Acta Materialia, Vol. 136
DOI: 10.1016/j.actamat.2017.07.013

On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options
journal, September 2021

Agarwal, S.; Lin, Y.; Li, C.
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 503
DOI: 10.1016/j.nimb.2021.06.018

Similar Records in DOE PAGES and OSTI.GOV collections:

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys

Journal Article Lin, Yan-Ru ; Bhattacharya, Arunodaya ; Chen, Da ; ... - Acta Materialia

Fe-Cr ferritic-martensitic (FM) steels are promising structural material candidates for fusion and advanced fission reactors due to their attractive mechanical properties and volumetric swelling resistance. However, significant discrepancies exist regarding the effect of solutes and irradiation temperature on cavity swelling under ion versus neutron irradiation conditions. In this study, simultaneous dual ion irradiations (8 MeV Ni³⁺ ions and energy-degraded 3.5 MeV He²⁺ ions) were used to quantify the cavity swelling behavior in ultra-high purity Fe and Fe-Cr alloys (3-14 wt.% Cr), Fe-10 wt.% Cr-780 wt.ppm C, and Eurofer97 FM steel. The irradiations were conducted over a wide temperature range (400-550°C)more »« less
https://doi.org/10.1016/j.actamat.2021.116660

Full Text Available
The role of Cr concentration and temperature on cavity swelling with co-injected helium in dual-ion irradiated Fe and Fe-Cr alloys

Journal Article Lin, Yan-Ru ; Bhattacharya, Arunodaya ; Chen, Da ; ... - Materials & Design

The level of chromium plays an essential role in irradiation tolerance of Fe-Cr ferritic alloys. However, conflicting results have been reported regarding the dependence of cavity swelling under irradiation on Cr level and temperature. Here, we have performed a comprehensive set of simultaneous dual-ion (Ni + He) irradiations to high dose (~30 displacements per atom, dpa) at 400–550 °C on a series of ultra-high purity Fe and Fe-Cr binary alloys (3–14 wt.%Cr). Helium co-implantation rates of 0.1 and 10 appm He/dpa were selected to examine He synergistic effects relevant for fission and fusion reactor conditions, respectively. Cavities were observed inmore »« less
https://doi.org/10.1016/j.matdes.2022.111134

Full Text Available
Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C

Journal Article Lin, Yan-Ru ; Chen, Wei-Ying ; Li, Meimei ; ... - Acta Materialia

The attractive mechanical properties and superior resistance to void-swelling make ferritic/martensitic alloys a promising structural material for advanced nuclear reactors. However, one anomaly that has intrigued researchers for more than 50 years is the proportion of two types of dislocation loops in Fe and Fe-Cr alloys with Burger vectors b=½<111> and b=<100>. Although the possible mechanisms responsible for the presence of <100> loops continue to be the subject of intense modeling studies, there remains incomplete experimental understanding of fundamental irradiation processes in Fe(Cr) alloys. Here, the dose dependence of the irradiation-induced microstructural evolution was examined from 0 to 20 displacementmore »« less
https://doi.org/10.1016/j.actamat.2021.116793

Full Text Available
Ion damage microstructures in a Fe-10Cr-6Mo-0. 5Nb ferritic steel

Conference Farrell, K ; Lee, E H

An annealed-and-aged ferritic steel containing fine NbC precipitates and relatively coarse particles of Laves phase was bombarded with 4-MeV iron ions to 100 displacements per atom (dpa) at 400 to 600/sup 0/C. Much of the damage structure consisted of dislocation tangles that coarsened with increasing temperature. Cavity formation began at 450/sup 0/C, peaked at 500 to 550/sup 0/C and was absent at 600/sup 0/C. Maximum swelling was only 0.2%. The Laves particles exhibited recoil dissolution and restructuring. Bombardments with Fe + He + D or Fe + He beams at ratios of 10 atomic parts per million (appM) He/dpa andmore »« less
Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials

Journal Article Clowers, Logan N. ; Jiao, Zhijie ; Was, Gary S. - Journal of Nuclear Materials

Three ferritic/martensitic alloys were studied to understand the synergistic effect between single ion beam (Fe²⁺), dual ion beam (Fe²⁺+He²⁺ and Fe²⁺+H⁺), and triple ion beam (Fe²⁺+He²⁺+H⁺) irradiations on cavity evolution. A commercial alloy, F82H, a castable nanostructured alloy, CNA3, and a high purity model alloy, Fe8Cr2W, were irradiated at 400°C to 600°C to a damage level of 50 dpa at a damage rate of 1 × 10^–3 dpa/s with He and H injection rates of 10 and 40 appm/dpa, respectively. Post-irradiation characterization via bright field transmission electron microscopy and high-angle annular dark-field scanning transmission electron microscopy was performed on allmore »« less
https://doi.org/10.1016/j.jnucmat.2022.153722

Full Text Available

Similar Records

Title: The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys

Abstract

Citation Formats

Materials challenges in nuclear energy journal, February 2013

On the origin of primary ½ a0 <111> and a0 <100> loops in irradiated Fe(Cr) alloys journal, July 2017

Fissile core and Tritium-Breeding Blanket: structural materials and their requirements journal, April 2008

Atomic Configuration of Point Defect Clusters in Ion-Irradiated Silicon Carbide journal, November 2017

The influence of helium on cavity evolution in ion-irradiated T91 journal, October 2018

Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys journal, November 2020

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys journal, April 2021

Critical radius for bias-driven swelling — a further analysis and its application to bimodal cavity size distributions journal, August 1983

Experimental effects of helium on cavity formation during irradiation—a review journal, January 1980

Helium and point defect accumulation: (i) microstructure and mechanical behaviour journal, April 2008

Mechanisms of helium interaction with radiation effects in metals and alloys: A review journal, November 1983

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation journal, August 2012

Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300°C and 400°C journal, December 2000

Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys journal, December 2021

Microstructural evolution in dual-ion irradiated 316ss under various helium injection schedules journal, May 1984

Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic/martensitic alloys journal, April 1990

Simulation irradiation studies on iron journal, January 1981

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications journal, June 2017

Neutronics aspects of the FESS-FNSF journal, October 2018

Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory journal, August 1978

Formulation of voids and bubbles as biased sinks to crystalline point defects journal, May 2021

He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40wt.% Cr: A transmission electron microscopy study journal, August 2013

Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation journal, May 2018

The effect of radiation upon diffusion in metals journal, February 1978

Analytical solutions for helium bubble and critical radius parameters using a hard sphere equation of state journal, April 1985

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments journal, October 2020

On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science journal, January 2018

The Role of Co-injected Helium on Swelling and Cavity Evolution at High Damage Levels in Ferritic-Martensitic Steels journal, July 2021

14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation journal, December 1990

55Fe effect on enhancing ferritic steel He/dpa ratio in fission reactor irradiations to simulate fusion conditions journal, November 2013

Molecular statics calculations of the biases and point defect capture volumes of small cavities journal, February 2018

Atomic configuration of irradiation-induced planar defects in 3C-SiC journal, March 2014

Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys journal, October 2013

Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications journal, November 2014

A dual ion irradiation study of helium–dpa interactions on cavity evolution in tempered martensitic steels and nanostructured ferritic alloys journal, June 2014

Radiation and helium effects on microstructures, nano-indentation properties and deformation behavior in ferrous alloys journal, December 2003

Dramatic reduction of void swelling by helium in ion-irradiated high purity α -iron journal, April 2018

Helium accumulation in metals during irradiation – where do we stand? journal, December 2003

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors journal, December 2003

Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injection journal, February 2014

Simulation of first wall damage: Effects of the method of gas implantation journal, December 1979

Multiscale modelling of defect kinetics in irradiated iron journal, December 2004

Cavity growth mechanism maps journal, October 1984

Predicting structural material degradation in advanced nuclear reactors with ion irradiation journal, February 2021

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9 journal, July 2015

II. Effect of oxygen and helium on void formation in metals journal, January 1987

Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C journal, May 2021

The effect of stress on the microstructure of neutron irradiated cold worked type 316 stainless steel journal, January 1974

Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures journal, September 2021

Comparison between bulk and thin foil ion irradiation of ultra high purity Fe journal, November 2013

Materials for future nuclear energy systems journal, December 2019

Designing Radiation Resistance in Materials for Fusion Energy journal, July 2014

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys journal, October 2015

Effect of saddle point anisotropy of point defects on their absorption by dislocations and cavities journal, September 2017

On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options journal, September 2021

Materials challenges in nuclear energy
journal, February 2013

On the origin of primary ½ a0 <111> and a0 <100> loops in irradiated Fe(Cr) alloys
journal, July 2017

Fissile core and Tritium-Breeding Blanket: structural materials and their requirements
journal, April 2008

Atomic Configuration of Point Defect Clusters in Ion-Irradiated Silicon Carbide
journal, November 2017

The influence of helium on cavity evolution in ion-irradiated T91
journal, October 2018

Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys
journal, November 2020

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys
journal, April 2021

Critical radius for bias-driven swelling — a further analysis and its application to bimodal cavity size distributions
journal, August 1983

Experimental effects of helium on cavity formation during irradiation—a review
journal, January 1980

Helium and point defect accumulation: (i) microstructure and mechanical behaviour
journal, April 2008

Mechanisms of helium interaction with radiation effects in metals and alloys: A review
journal, November 1983

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation
journal, August 2012

Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300°C and 400°C
journal, December 2000

Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys
journal, December 2021

Microstructural evolution in dual-ion irradiated 316ss under various helium injection schedules
journal, May 1984

Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic/martensitic alloys
journal, April 1990

Simulation irradiation studies on iron
journal, January 1981

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017

Neutronics aspects of the FESS-FNSF
journal, October 2018

Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
journal, August 1978

Formulation of voids and bubbles as biased sinks to crystalline point defects
journal, May 2021

He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40wt.% Cr: A transmission electron microscopy study
journal, August 2013

Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation
journal, May 2018

The effect of radiation upon diffusion in metals
journal, February 1978

Analytical solutions for helium bubble and critical radius parameters using a hard sphere equation of state
journal, April 1985

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
journal, October 2020

On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science
journal, January 2018

The Role of Co-injected Helium on Swelling and Cavity Evolution at High Damage Levels in Ferritic-Martensitic Steels
journal, July 2021

14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation
journal, December 1990

55Fe effect on enhancing ferritic steel He/dpa ratio in fission reactor irradiations to simulate fusion conditions
journal, November 2013

Molecular statics calculations of the biases and point defect capture volumes of small cavities
journal, February 2018

Atomic configuration of irradiation-induced planar defects in 3C-SiC
journal, March 2014

Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys
journal, October 2013

Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications
journal, November 2014

A dual ion irradiation study of helium–dpa interactions on cavity evolution in tempered martensitic steels and nanostructured ferritic alloys
journal, June 2014

Radiation and helium effects on microstructures, nano-indentation properties and deformation behavior in ferrous alloys
journal, December 2003

Dramatic reduction of void swelling by helium in ion-irradiated high purity α -iron
journal, April 2018

Helium accumulation in metals during irradiation – where do we stand?
journal, December 2003

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors
journal, December 2003

Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injection
journal, February 2014

Simulation of first wall damage: Effects of the method of gas implantation
journal, December 1979

Multiscale modelling of defect kinetics in irradiated iron
journal, December 2004

Cavity growth mechanism maps
journal, October 1984

Predicting structural material degradation in advanced nuclear reactors with ion irradiation
journal, February 2021

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
journal, July 2015

II. Effect of oxygen and helium on void formation in metals
journal, January 1987

Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C
journal, May 2021

The effect of stress on the microstructure of neutron irradiated cold worked type 316 stainless steel
journal, January 1974

Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures
journal, September 2021

Comparison between bulk and thin foil ion irradiation of ultra high purity Fe
journal, November 2013

Materials for future nuclear energy systems
journal, December 2019

Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015

Effect of saddle point anisotropy of point defects on their absorption by dislocations and cavities
journal, September 2017

On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options
journal, September 2021