Hydrogen traps in ion-irradiated F82H steel observed by NRA

Takagi, Ikuji; Komura, Takahiro; Akiyoshi, Masafumi; Moritani, Kimikazu; Sasaki, Takayuki; Moriyama, Hirotake

doi:10.1016/j.jnucmat.2013.04.057

Cited by 12 publications

(7 citation statements)

References 20 publications

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“…Instead, in-operando measurements during plasma exposure are required to explore dynamic retention. Several studies on dynamic D retention in graphite [12,13,15] and metals [14][15][16] have been conducted using in-operando IBA measurements. For instance, the D retention in Mo was measured with NRA (integrated up to ∼5 μm in depth) under D plasma exposure (incident ion flux = 1.8 × 10 21 m −2 s −1 , target bias voltage = −100 V, and sample temperature = 300 K) [14].…”

Section: Introductionmentioning

confidence: 99%

Dynamic deuterium retention properties of tungsten measured using laser-induced breakdown spectroscopy

Nishijima¹,

Doerner²,

Baldwin³

et al. 2021

Nucl. Fusion

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Dynamic deuterium (D) retention properties of tungsten (W) are investigated under steady-state D plasma exposure in the PISCES-A linear plasma device. In contrast to static retention, dynamic retention is quickly released from the material at the termination of the incident plasma flux, and thus in-operando laser-induced breakdown spectroscopy (LIBS) measurements have been conducted during steady-state D plasma exposure. A procedure is, first, established to extract the dynamic retention component from the in-operando LIBS D I 656.1 nm line intensity, which can contain contributions from dynamic and static retention as well as background D/D2 gas, excited by both steady-state and laser-induced plasmas. Using the developed procedure, the dynamic D retention in W is systematically examined while scanning the following plasma exposure parameters: incident ion energy, E i, sample temperature, T s, incident ion flux, Γi. No clear E i dependence is seen in the range of E i ∼ 45–175 eV, as expected from a small variation in the average implantation depth (∼3–6 nm) of D in W. The dynamic retention is found to monotonously decrease with increasing T s from 348 to 573 K, while the total static retention is reported to peak at T s ∼ 500–600 K. It is revealed that the dynamic retention linearly increases with increasing Γi, and then saturates at Γi ⩾ 0.75 × 1021 m−2 s−1. Possible physical mechanisms for the observed dependence of the dynamic retention on T s and Γi are discussed. Furthermore, sequential pure He, followed by pure D, plasma exposures show that the dynamic D retention is not strongly affected by He bubbles in the near-surface region.

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Section: Introductionmentioning

confidence: 99%

Dynamic deuterium retention properties of tungsten measured using laser-induced breakdown spectroscopy

Nishijima¹,

Doerner²,

Baldwin³

et al. 2021

Nucl. Fusion

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“…In [51], hydrogen trapping characteristics in ionirradiated F82H (e.g., the trapping energy, the production rate, and the annihilation temperature) were determined. Traps were produced by 0.8 MeV 4 He or 0.3 MeV H ion irradiation.…”

Section: Fig 1 Experimental (Black Point) and Calculated (Grey Curve)...mentioning

confidence: 99%

Helium and Hydrogen Effects in Structural Materials for Nuclear Applications

Karpov¹,

Tolstolutskaya²

2022

Problems of Atomic Science and Technology

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Displacement cascades produce a variety of defects under reactor conditions, but of particular concern is the simultaneous production of helium (He) and hydrogen (H), which enhances the degradation of structural materials. The overall majority of performed studies on helium and hydrogen interactions with materials were based on ion beam irradiation, which served as a convenient tool for the simulation of neutrons exposure over a variety of temperature and dose regimes due to the ability to widely vary and control the irradiation parameters. Experimental investigations of the hydrogen-defect interaction performed by thermal desorption spectroscopy, and the parameters of this interaction obtained by numerical simulations based on diffusion-trapping codes are debated. In this review, we also summarize previous studies on grain boundaries and nanoprecipitate effects on hydrogen transport in metals, as well as the role of hydrogen in the corrosion and cracking of steels. We discuss here issues of helium bubbles formation and some of the evidence for the synergistic effects of hydrogen and helium in the presence of displacement damage, and their influence on irradiation hardening and swelling. Particular attention was devoted to the features of hydrogen interaction with noble-gas bubbles, which were considered on the basis of most recent published data.

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“…In the last few years, experiments have provided a considerable database on the D retention in undamaged and damaged RAFM and RAFM/RAF-ODS steels irradiated with D ions and exposed to D plasmas [12,13,14,15,16,17,18,19,20,21,22,23,24,25,26,27]. In Refs.…”

Section: Reduced Activation Ferritic/martensitic (Rafm) Steels Includmentioning

confidence: 99%

“…In Refs. [20][21][22][23][24][25][26][27], the depth distributions of D concentration in undamaged and damaged steels were determined by nuclear reaction analysis (NRA) at depths of up to several micrometers.…”

Section: Reduced Activation Ferritic/martensitic (Rafm) Steels Includmentioning

confidence: 99%

Surface modification and deuterium retention in reduced-activation steels exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas

Alimov

Огородникова

Hatano

et al. 2018

Journal of Nuclear Materials

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Surface topography of and deuterium (D) retention in reduced activation ferritic-martensitic Eurofer'97 and ferritic oxide dispersion strengthening ODS-16Cr steels have been studied after exposure at 600 K to low-energy (70 and 200 eV), high-flux (~10 22 D/m 2 s) pure D and D-10%He plasmas with D fluence of 2×10 25 D/m 2. The methods used were scanning electron microscopy, energy-scanning D(3 He,p) 4 He nuclear reaction, and thermal desorption spectroscopy. As a result of the plasma exposures, nano-sized structures are formed on the steel surfaces. After exposure to pure D plasmas, a significant fraction of D is accumulated in the bulk, at depths larger than 8 µm. After exposures to D-He plasmas, D is retained mainly in the near-surface layers. In spite of the fact that the He fluence was lower than the D fluence, the He retention in the steels is one order of magnitude higher than the D retention.

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Hydrogen traps in ion-irradiated F82H steel observed by NRA

Cited by 12 publications

References 20 publications

Dynamic deuterium retention properties of tungsten measured using laser-induced breakdown spectroscopy

Dynamic deuterium retention properties of tungsten measured using laser-induced breakdown spectroscopy

Helium and Hydrogen Effects in Structural Materials for Nuclear Applications

Surface modification and deuterium retention in reduced-activation steels exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas

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