Positron annihilation spectroscopy evaluation of using proton irradiation as a surrogate for early neutron radiation damage
Source abstract
Abstract
• Proton implantation can be used for a simulation of an early-stage neutron damage. • Temperature influences recombination and mobility of defects and hydrogen. • The ODS microstructure clearly affects on radiation stability and defect migration. • Hydrogen has a visible effect on the stabilization of vacancies. A positron annihilation spectroscopy investigation of early stages of radiation-induced damage in Chinese f/m (ferritic/martensitic) steel SIMP and strengthened variant of f/m steel ODS (oxide dispersion strengthened) EUROFER was conducted. Studied materials were irradiated by neutrons at the LVR-15 research reactor to 0.12 dpa at an average temperature of 260 ± 20 °C, and implanted by protons at the 6 MV Tandetron Accelerator of the Slovak University of Technology, to 0.0196 dpa at room temperature (RT) and 300 °C. The potential of using proton irradiation as a surrogate for early neutron radiation damage was investigated. A lifetime spectrometer and Doppler spectrometer was used to obtain simultaneously positron lifetime (PALS) and Doppler broadening spectra (DBS), which provided experimental data used to characterize the vacancy-type defect and their interaction with H atoms in the studied materials. The obtained results show an increase of mean positron lifetime (MLT) in the proton-implanted samples at RT when compared with high temperature irradiation. Similar trend was observed when comparing vacancy concentration of different irradiation conditions. The impact of temperature on mobility and recombination of defects, as well as effect of vacancy stabilization by H atoms, has been addressed. The effect of ODS microstructure on results has been examined. A methodology of comparing various irradiation conditions has been proposed, where the vacancy concentrations have been normalized by the dpa values. The potential application of proton implantation for evaluation of early stages of neutron damage was found to be promising.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Fusion materials and technologies · Muon and positron interactions and applications · Ion-surface interactions and analysis
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (32)
Show source-provided references
1. Energy production and consumption
2. Exploring the role of nuclear energy in the energy transition: a comparative perspective of the effects of coal, oil, natural gas, renewable energy, and nuclear power on economic growth and carbon emissions10.1016/j.envres.2023.115290 ↗
3. Structural materials for fission & fusion energy10.1016/S1369-7021(09)70294-9 ↗
4. Analysis of the possible contribution of different nuclear fusion technologies to the global energy transition10.1016/j.esr.2023.101144 ↗
5. Economic, safety and environmental prospects of fusion reactors10.1088/0029-5515/30/9/015 ↗
6. Materials for future nuclear energy systems10.1016/j.jnucmat.2019.151837 ↗
7. Ferritic-martensitic steels for fission and fusion applications10.1016/j.jnucmat.2019.05.058 ↗
8. Ukai · 2012 · 4
9. Evaluation of irradiation facility options for fusion materials research and development10.1016/j.fusengdes.2013.02.081 ↗
10. Simulation of neutron irradiation damage in tungsten using higher energy protons10.1016/j.nme.2016.09.008 ↗
11. Influence of temperature on the microstructural evolution of SIMP and T91 steels in liquid lead-bismuth eutectic: experiments and molecular dynamics simulations10.1016/j.corsci.2023.111411 ↗
12. High-resolution transmission electron microscopy and electron backscatter diffraction in nanoscaled ferritic and ferritic–martensitic oxide dispersion strengthened–steels10.1016/j.jnucmat.2008.11.029 ↗
13. Silicon enhances high temperature oxidation resistance of SIMP steel at 700 °C10.1016/j.corsci.2020.108519 ↗
14. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts10.1016/j.fusengdes.2005.06.186 ↗
15. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
16. A proposed method of calculating displacement dose rates10.1016/0029-5493(75)90035-7 ↗
17. Positron annihilation spectroscopy studies of irradiated Fe-based alloys using different radioisotope sources10.1016/j.nimb.2018.08.031 ↗
18. Helium behavior in ferritic/martensitic steels irradiated in spallation target10.1016/j.jnucmat.2014.10.014 ↗
19. Positron annihilation studies of Eurofer97/ODS steels after helium ion implantation
20. LT10 Program for Solving Basic Problems Connected with Defect Detection10.1016/j.phpro.2012.06.022 ↗
21. Characterization of lattice defects in metallic materials by positron annihilation spectroscopy: a review10.1016/j.jmst.2017.11.050 ↗
22. Defect spectroscopy with positrons: a general calculational method10.1088/0305-4608/13/2/009 ↗
23. On the empirical determination of positron trapping coefficient at nano-scale helium bubbles in steels irradiated in spallation target10.1016/j.jnucmat.2018.03.045 ↗
24. Positron lifetime study of reactor pressure vessel steels10.1002/1521-396X(200004)178:2<651::AID-PSSA651>3.0.CO;2-O ↗
25. Positron trapping rate into vacancy clusters10.1007/BF00885942 ↗
26. Review of defect investigations by means of positron annihilation in II-VI compound semiconductors10.1007/s003390050721 ↗
27. Positron annihilation spectroscopy of defects in nuclear and irradiated materials- a review10.1016/j.matchar.2021.110952 ↗
28. He · 2014
29. Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation10.1016/j.nimb.2017.05.024 ↗
30. Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation10.1016/j.jnucmat.2007.03.016 ↗
31. Radiation-induced precipitates in ferritic-martensitic steels and their radiation resistance effects
32. On the helium bubble swelling in nano-oxide dispersion-strengthened steels10.1016/j.jmst.2021.08.004 ↗