Tungsten (W) is a leading plasma-facing material candidate for future fusion reactors thanks to its outstanding properties. Under fusion-relevant conditions, it will be exposed to 14 MeV neutrons, creating lattice defects that trap hydrogen isotopes, thereby affecting hydrogen transport and retention. To simulate neutron-induced damage, MeV self-ion irradiation is commonly used. The resulting defects are then decorated with deuterium (D) using D plasma. D concentration profiles are measured by nuclear reaction analysis (NRA), while binding states are identified through thermal desorption spectroscopy (TDS). Previous studies show that at 290 K trapped D concentration saturates above 0.1 dpa. However, despite the same final trapped D concentration at 0.23 and 2.3 dpa, the 2.3 dpa sample shows a significantly slower D uptake rate, which cannot be explained by current reaction–diffusion models. In this study, recrystallized polycrystalline (PC) and (111) single crystalline (SC) W samples were irradiated with 20 MeV self-ions to 0.23 and 2.3 dpa at 290 K. To assess temperature effects, irradiation to 2.3 dpa at 1350 K was also performed. Samples were simultaneously exposed to low-flux D plasma at 370 K for different times (8-384 h), and D uptake kinetics were monitored by NRA. For samples damaged to 0.23 dpa, all defects were decorated after 72 h of exposure. In contrast, PC W irradiated to 2.3 dpa (290 K) required 192 h, and SC W reached the same total retained D after 384 h. The PC sample damaged to 2.3 dpa (1350 K) also required 192 h with similar D concentration. However, at 1350 K the SC sample shows D concentration about four times lower than the PC, highlighting the strong influence of microstructure at high irradiation temperatures. TDS showed a change in dominant defect types: vacancies and vacancy clusters at 290 K, and nm voids at 1350 K, consistent with atomistic simulations. D retention values from NRA and TDS agreed well for PC samples and SC at 0.23 dpa (290 K), while significant deviations were observed for SC damaged to 2.3 dpa.
Il tungsteno (W) è un promettente candidate per i materiali di prima parete nei futuri reattori a fusione, grazie alle sue eccellenti proprietà. In esercizio sarà esposto a neutroni da 14 MeV, che producono difetti reticolari che intrappolano gli isotopi dell’idrogeno, modificandone trasporto e ritenzione nel materiale. Il danno da neutroni viene simulato tramite autoirraggiamento con ioni MeV. I difetti generati sono in seguito decorati tramite esposizione a plasma di deuterio (D); i profili di concentrazione sono determinati con analisi per reazione nucleare (NRA), mentre le energie di legame sono investigate con spettroscopia di desorbimento termico (TDS). Studi precedenti mostrano che per irraggiamenti a 290 K, la concentrazione di D intrappolato raggiunge saturazione dopo 0,1 dpa. Tuttavia, a parità di concentrazione, il campione irradiato a 2,3 dpa presenta una cinetica di assorbimento più lenta rispetto a quello irradiato a 0,23 dpa, in contrasto con gli attuali modelli. In questo lavoro, campioni di W policristallino ricristallizzato (PC) e monocristallino (SC) (111) sono stati irradiati con ioni da 20 MeV a 290 K a 0,23 e 2,3 dpa; è stato inoltre effettuato un irraggiamento a 2,3 dpa a 1350 K. I campioni sono stati quindi esposti a plasma di D a basso flusso e energia a 370 K, monitorando la cinetica di assorbimento tramite NRA. I campioni irradiati a 0,23 dpa(290 K) mostrano decorazione dei difetti dopo 72 h. Il PC irradiato a 2,3 dpa (290 K) richiede 192 h, mentre lo SC raggiunge la stessa ritenzione totale dopo 384 h. Il PC irradiato a 2,3 dpa a 1350 K presenta ritenzione simile e decorazione in 192 h. Tuttavia, a 1350 K la ritenzione di D nel PC è circa tre volte superiore rispetto allo SC, evidenziando l’influenza della microstruttura ad alte temperature. La TDS evidenzia inoltre un cambiamento nei difetti dominanti: vacanze e cluster di vacanze a 290 K, vuoti nanometrici a 1350 K, in accordo con simulazioni atomistiche. Buon accordo tra NRA e TDS si osserva nei PC e nello SC a 0,23 dpa, mentre emergono deviazioni negli SC a 2,3 dpa.
Kinetics of deuterium uptake in self-ion irradiated tungsten at different temperatures
AGNOLI, DIEGO
2024/2025
Abstract
Tungsten (W) is a leading plasma-facing material candidate for future fusion reactors thanks to its outstanding properties. Under fusion-relevant conditions, it will be exposed to 14 MeV neutrons, creating lattice defects that trap hydrogen isotopes, thereby affecting hydrogen transport and retention. To simulate neutron-induced damage, MeV self-ion irradiation is commonly used. The resulting defects are then decorated with deuterium (D) using D plasma. D concentration profiles are measured by nuclear reaction analysis (NRA), while binding states are identified through thermal desorption spectroscopy (TDS). Previous studies show that at 290 K trapped D concentration saturates above 0.1 dpa. However, despite the same final trapped D concentration at 0.23 and 2.3 dpa, the 2.3 dpa sample shows a significantly slower D uptake rate, which cannot be explained by current reaction–diffusion models. In this study, recrystallized polycrystalline (PC) and (111) single crystalline (SC) W samples were irradiated with 20 MeV self-ions to 0.23 and 2.3 dpa at 290 K. To assess temperature effects, irradiation to 2.3 dpa at 1350 K was also performed. Samples were simultaneously exposed to low-flux D plasma at 370 K for different times (8-384 h), and D uptake kinetics were monitored by NRA. For samples damaged to 0.23 dpa, all defects were decorated after 72 h of exposure. In contrast, PC W irradiated to 2.3 dpa (290 K) required 192 h, and SC W reached the same total retained D after 384 h. The PC sample damaged to 2.3 dpa (1350 K) also required 192 h with similar D concentration. However, at 1350 K the SC sample shows D concentration about four times lower than the PC, highlighting the strong influence of microstructure at high irradiation temperatures. TDS showed a change in dominant defect types: vacancies and vacancy clusters at 290 K, and nm voids at 1350 K, consistent with atomistic simulations. D retention values from NRA and TDS agreed well for PC samples and SC at 0.23 dpa (290 K), while significant deviations were observed for SC damaged to 2.3 dpa.| File | Dimensione | Formato | |
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https://hdl.handle.net/10589/251539