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Title: Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling

Journal Article · · Materials Research Letters
 [1];  [1];  [2];  [1];  [2];  [1]
  1. Texas A & M Univ., College Station, TX (United States)
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Although accelerator-based ion irradiation has been widely accepted to simulate neutron damage, neutron-atypical features need to be carefully investigated. In this study, we have shown that Coulomb force drag by ion beams can introduce significant amounts of carbon, nitrogen, and oxygen into target materials even under ultra-high vacuum conditions. The resulting compositional and microstructural changes dramatically suppress void swelling. By applying a beam-filtering technique, introduction of vacuum contaminants is greatly minimized and the true swelling resistance of the alloys is revealed and matches neutron behavior closely. These findings are a significant step toward developing standardized procedures for emulating neutron damage.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC52-06NA25396; NE0008297
OSTI ID:
1422930
Report Number(s):
LA-UR-18-20847; TRN: US1801674
Journal Information:
Materials Research Letters, Vol. 5, Issue 7; ISSN 2166-3831
Publisher:
Taylor and FrancisCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 38 works
Citation information provided by
Web of Science

References (21)

Radiation Damage in Austenitic Steels book January 2012
Void swelling and irradiation creep in light water reactor (LWR) environments book January 2010
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure journal January 2000
Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor journal December 2000
Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions journal October 2014
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C journal October 2015
Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage journal July 1983
Simulated spatial and temporal dependence of chromium concentration in pure Fe and Fe 14%Cr under high dpa ion irradiation journal October 2016
Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling
  • Wang, Jing; Toloczko, Mychailo B.; Bailey, Nathan
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 387 https://doi.org/10.1016/j.nimb.2016.09.015
journal November 2016
Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ~ 400°C journal September 1994
Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa journal October 1996
Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C journal September 2009
Radiation response of alloy T91 at damage levels up to 1000 peak dpa journal December 2016
SRIM – The stopping and range of ions in matter (2010)
  • Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12 https://doi.org/10.1016/j.nimb.2010.02.091
journal June 2010
On the use of SRIM for computing radiation damage exposure journal September 2013
Modeling injected interstitial effects on void swelling in self-ion irradiation experiments journal April 2016
Recent Developments in Irradiation-Resistant Steels journal August 2008
Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation journal December 2015
Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces journal September 2016
Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels journal November 2016
Void swelling in ferritic-martensitic steels under high dose ion irradiation: Exploring possible contributions to swelling resistance journal February 2016

Cited By (7)

Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels journal November 2017
Study of Nanostructure of Ferritic-Martensitic Steel ChS-139 in Initial State and after Fe Ion Irradiation journal March 2018
Magnetic Properties of Proton Irradiated Mn3Si2Te6 van der Waals Single Crystals journal January 2019
Magnetic Properties of Proton Irradiated Fe2.7GeTe2 Bulk Crystals journal January 2019
The Effect of Internal Free Surfaces on Void Swelling of Irradiated Pure Iron Containing Subsurface Trenches journal May 2019
Microstructure and Mechanical Properties of Ti + N Ion Implanted Cronidur30 Steel journal January 2019
Effect of Helium on Dispersoid Evolution under Self-Ion Irradiation in A Dual-Phase 12Cr Oxide-Dispersion-Strengthened Alloy journal October 2019

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