Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications
Terentyev, Dmitry ; Rieth, Michael
1; Pintsuk, Gerald; Müller, Alexander von; Antusch, Steffen 2,3; Zinovev, Aleksandr; Bakaev, Alexander; Poleshchuk, Kateryna; Aiello, Giacomo
1 Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP), Karlsruher Institut für Technologie (KIT)
2 Institut für Angewandte Materialien – Werkstoffkunde (IAM-WK), Karlsruher Institut für Technologie (KIT)
3 Karlsruher Institut für Technologie (KIT)
1; Pintsuk, Gerald; Müller, Alexander von; Antusch, Steffen 2,3; Zinovev, Aleksandr; Bakaev, Alexander; Poleshchuk, Kateryna; Aiello, Giacomo1 Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP), Karlsruher Institut für Technologie (KIT)
2 Institut für Angewandte Materialien – Werkstoffkunde (IAM-WK), Karlsruher Institut für Technologie (KIT)
3 Karlsruher Institut für Technologie (KIT)
Abstract (englisch):
The effect of neutron irradiation on tensile properties and fracture mode has been investigated for several
advanced CuCrZr alloys in the frame of the European fusion material development program. Five material grades
utilizing different strengthening principles have been exposed to neutron irradiation up to ~2.5 dpa (displacement
per atom) in the target operational temperature range of 150–450 ◦C. The strengthening mechanisms are
based on the application of: i) tungsten particles; ii) tungsten foils (laminate structure); iii) tungsten fibers; iv)
Y2O3 particles; v) vanadium addition (0.22%). Neutron irradiation was performed in the BR2 material test
reactor inside the fuel channel in order to maximize the fast neutron flux. The upper irradiation temperature of
450 ◦C was selected to validate the ability of the pre-selected advanced grades to sustain the high temperature
irradiation, since the baseline ITER specification CuCrZr is known not to retain sufficient tensile strength above
400 ◦C in non-irradiated conditions and shows strong irradiation induced softening above 300 ◦C. Neutron
irradiation at 150 ◦C caused severe embrittlement of tungsten-copper laminates as well as a considerable
... mehr
advanced CuCrZr alloys in the frame of the European fusion material development program. Five material grades
utilizing different strengthening principles have been exposed to neutron irradiation up to ~2.5 dpa (displacement
per atom) in the target operational temperature range of 150–450 ◦C. The strengthening mechanisms are
based on the application of: i) tungsten particles; ii) tungsten foils (laminate structure); iii) tungsten fibers; iv)
Y2O3 particles; v) vanadium addition (0.22%). Neutron irradiation was performed in the BR2 material test
reactor inside the fuel channel in order to maximize the fast neutron flux. The upper irradiation temperature of
450 ◦C was selected to validate the ability of the pre-selected advanced grades to sustain the high temperature
irradiation, since the baseline ITER specification CuCrZr is known not to retain sufficient tensile strength above
400 ◦C in non-irradiated conditions and shows strong irradiation induced softening above 300 ◦C. Neutron
irradiation at 150 ◦C caused severe embrittlement of tungsten-copper laminates as well as a considerable
... mehr
| Zugehörige Institution(en) am KIT | Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP) Institut für Angewandte Materialien – Werkstoffkunde (IAM-WK) |
| Publikationstyp | Zeitschriftenaufsatz |
| Publikationsmonat/-jahr | 10.2023 |
| Sprache | Englisch |
| Identifikator | ISSN: 0022-3115 KITopen-ID: 1000160298 |
| HGF-Programm | 31.13.05 (POF IV, LK 01) Neutron-Resistant Structural Materials |
| Erschienen in | Journal of Nuclear Materials |
| Verlag | Elsevier |
| Band | 584 |
| Seiten | Article no: 154587 |
| Schlagwörter | Copper. Irradiation, Alloys, Composites |
| Nachgewiesen in | Dimensions Web of Science Scopus |
| Globale Ziele für nachhaltige Entwicklung |