Heavy ion irradiation response of an additively manufactured 316LN stainless steel
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Title
Heavy ion irradiation response of an additively manufactured 316LN stainless steel
Authors
Keywords
Additively manufactured 316LN SS, solidification cellular structures, heavy ion irradiation, dislocation loops, chemical segregation
Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 546, Issue -, Pages 152745
Publisher
Elsevier BV
Online
2020-12-26
DOI
10.1016/j.jnucmat.2020.152745
References
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- Influence of injected interstitials on the void swelling in two structural variants of 304L stainless steel induced by self-ion irradiation at 500 °C
- (2017) C. Sun et al. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
- Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials
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- (2017) Jonathan G. Gigax et al. Materials Research Letters
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- (2016) Jun Takahashi et al. ACTA MATERIALIA
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- (2015) Jonathan G. Gigax et al. JOURNAL OF NUCLEAR MATERIALS
- Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments
- (2015) C. Sun et al. Scientific Reports
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- Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation
- (2014) M. Song et al. ACTA MATERIALIA
- Metal Additive Manufacturing: A Review
- (2014) William E. Frazier JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE
- Emulation of reactor irradiation damage using ion beams
- (2014) G.S. Was et al. SCRIPTA MATERIALIA
- Estimation of grain boundary segregation enthalpy and its role in stable nanocrystalline alloy design
- (2013) Heather A. Murdoch et al. JOURNAL OF MATERIALS RESEARCH
- A systematic study of radiation-induced segregation in ferritic–martensitic alloys
- (2013) Janelle P. Wharry et al. JOURNAL OF NUCLEAR MATERIALS
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- Interplay between hydrogen and vacancies inα-Fe
- (2013) Erin Hayward et al. PHYSICAL REVIEW B
- Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys
- (2012) D. Terentyev et al. ACTA MATERIALIA
- Ab initiodescription of monovacancies in paramagnetic austenitic Fe-Cr-Ni alloys
- (2012) L. Delczeg et al. PHYSICAL REVIEW B
- Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation
- (2011) S. Choudhury et al. JOURNAL OF NUCLEAR MATERIALS
- Enhanced annealing of the dislocation network under irradiation
- (2011) Dan Mordehai et al. PHYSICAL REVIEW B
- SRIM – The stopping and range of ions in matter (2010)
- (2010) James F. Ziegler et al. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
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