Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings

Nakazawa, Shota; Nakamura, Kazuki; Fujita, Hideyuki; Maier, H.; Schwarz-Selinger, T.; Hatano, Yuji; Ashikawa, N.; Inami, Wataru; Kawata, Yoshimasa; Chikada, Takumi

doi:10.1016/j.jnucmat.2020.152321

Cited by 9 publications

(3 citation statements)

References 15 publications

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“…The detailed structure is shown in ref. [12]. The specimens were put into a metal chamber and heated up to 600 °C by an electric furnace under the pressure range of 10 -5 -10 -3 Pa. After the temperature reached 600 °C, D 2 gas at 0.8 or 80 kPa was introduced into the chamber and maintained for 6 or 24 h, respectively.…”

Section: Methodsmentioning

confidence: 99%

Thermal shock behavior under deuterium plasma exposure of tungsten–tantalum alloys

Nogami¹,

Wirtz²,

Lied³

et al. 2021

Phys. Scr.

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Tungsten-tantalum (W-Ta) alloys for the application to fusion reactor divertor were developed to overcome the issues of W related to the low temperature brittleness, embrittlement by recrystallization, and embrittlement by neutron irradiation. In the present study, the response to cyclic thermal shock tests as well as the fundamental mechanical properties of W-3%Ta and pure W were investigated, which simulated a transient heat load event in the actual divertor environment. Because it was concerned that the effect of deuterium (D) plasma exposure might be much more pronounced in the Ta-alloyed materials, the thermal shock tests were performed under the background steady state D-plasma exposure. Based on the present study, W-3%Ta might be a competitive alloy system from the viewpoint of thermo-mechanical response in the actual divertor environment as well as the fundamental mechanical properties and resistance to recrystallization. RECEIVED

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Section: Methodsmentioning

confidence: 99%

Thermal shock behavior under deuterium plasma exposure of tungsten–tantalum alloys

Nogami¹,

Wirtz²,

Lied³

et al. 2021

Phys. Scr.

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“…The studies of gamma irradiation effect on nuclear materials have been carried out for several decades in both experiments 4–14 and theory 15,16 . Sato et al.…”

Section: Introductionmentioning

confidence: 99%

“…[1][2][3] Therefore, the study of gamma irradiation effect on nuclear materials is important for nuclear engineering. The studies of gamma irradiation effect on nuclear materials have been carried out for several decades in both experiments [4][5][6][7][8][9][10][11][12][13][14] and theory. 15,16 Sato et al observed a highintensity luminescence in sapphire and quartz, which is induced by gamma irradiation.…”

Section: Introductionmentioning

confidence: 99%

Gamma‐ray irradiation effect on microstructure and physical performances of porous silica

et al. 2023

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In this paper, the gamma irradiation effect on the microstructure and physical performances of porous silica, including mechanical, thermal, and optical performances, are systematically investigated by using molecular dynamics and density‐functional theory‐based methods. The study of bond angle distribution, pair distribution function, coordination number distribution, and average ring size distribution show that, after gamma‐ray irradiation, the microstructure of porous silica is obviously modified. The tight packing of SiO2 tetrahedrons in the porous silica network is broken by gamma‐ray irradiation. Defects of three‐coordinated Si and non‐bridging oxygen are induced by gamma‐ray irradiation. Moreover, we find that the defects concentrations rapidly grow as gamma‐ray dose increases. The mechanical, thermal, and optical performances of porous silica are all seriously degenerated by gamma‐ray irradiation. Our results show that, for mechanical performance, Young's modulus, Bulk modulus, and Shear modulus first decrease and then keep stable as gamma‐ray dose increases, but the change of Poisson's ratio is slight. For thermal performance, the thermal conductivity decreases exponentially as gamma‐ray dose increases. For optical performance, light absorption coefficients increase exponentially and light transmittance drops as gamma‐ray dose increases in the working range (photon energy range around 3.5 eV) of inertial confinement fusion. Present work is expected to be valuable for studying the degradation mechanism of silicate materials under gamma radiation and developing gamma‐ray irradiation protection technology.

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Lithium-lead corrosion behavior of zirconium oxide coating after heavy-ion irradiation

Miura

Nakamura

Akahoshi

et al. 2021

Fusion Engineering and Design

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Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings

Cited by 9 publications

References 15 publications

Thermal shock behavior under deuterium plasma exposure of tungsten–tantalum alloys

Thermal shock behavior under deuterium plasma exposure of tungsten–tantalum alloys

Gamma‐ray irradiation effect on microstructure and physical performances of porous silica

Lithium-lead corrosion behavior of zirconium oxide coating after heavy-ion irradiation

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