Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti

H. Watanabe; T. Tokunaga; N. Yoshida; T. Nagasaka; T. Muroga

doi:10.1016/j.jnucmat.2013.02.051

Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti

H. Watanabe, T. Tokunaga, N. Yoshida, T. Nagasaka, T. Muroga

Division of Nuclear Fusion Dynamics

Research output: Contribution to journal › Article › peer-review

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Abstract

Microstructures of vacuum plasma sprayed (VPS) and brazed W on NIFS-HEAT-2 were studied by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). During the VPS process, growth of grains perpendicular to the interface was prominent. The blocky Ti-oxides, which have a strong effect on the mechanical properties before and after irradiation, were dissolved in the interface region of NIFS-HEAT-2. Understanding the effect of heat treatment (namely, post-coating heat treatment) on W-coated materials is important to reduce the irradiation induced hardening effects on the materials. After a heat load of about 5 MW/m² (∼16 cycles), the surface of VPS-W has a very fine rough structure but no prominent cracks due to thermal heat loads were detected.

Original language	English
Pages (from-to)	S292-S296
Journal	Journal of Nuclear Materials
Volume	442
Issue number	1-3 SUPPL.1
DOIs	https://doi.org/10.1016/j.jnucmat.2013.02.051
Publication status	Published - Apr 10 2013

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Materials Science(all)
Nuclear Energy and Engineering

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10.1016/j.jnucmat.2013.02.051

Cite this

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title = "Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti",

abstract = "Microstructures of vacuum plasma sprayed (VPS) and brazed W on NIFS-HEAT-2 were studied by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). During the VPS process, growth of grains perpendicular to the interface was prominent. The blocky Ti-oxides, which have a strong effect on the mechanical properties before and after irradiation, were dissolved in the interface region of NIFS-HEAT-2. Understanding the effect of heat treatment (namely, post-coating heat treatment) on W-coated materials is important to reduce the irradiation induced hardening effects on the materials. After a heat load of about 5 MW/m2 (∼16 cycles), the surface of VPS-W has a very fine rough structure but no prominent cracks due to thermal heat loads were detected.",

author = "H. Watanabe and T. Tokunaga and N. Yoshida and T. Nagasaka and T. Muroga",

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T1 - Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti

AU - Watanabe, H.

AU - Tokunaga, T.

AU - Yoshida, N.

AU - Nagasaka, T.

AU - Muroga, T.

PY - 2013/4/10

Y1 - 2013/4/10

N2 - Microstructures of vacuum plasma sprayed (VPS) and brazed W on NIFS-HEAT-2 were studied by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). During the VPS process, growth of grains perpendicular to the interface was prominent. The blocky Ti-oxides, which have a strong effect on the mechanical properties before and after irradiation, were dissolved in the interface region of NIFS-HEAT-2. Understanding the effect of heat treatment (namely, post-coating heat treatment) on W-coated materials is important to reduce the irradiation induced hardening effects on the materials. After a heat load of about 5 MW/m2 (∼16 cycles), the surface of VPS-W has a very fine rough structure but no prominent cracks due to thermal heat loads were detected.

AB - Microstructures of vacuum plasma sprayed (VPS) and brazed W on NIFS-HEAT-2 were studied by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). During the VPS process, growth of grains perpendicular to the interface was prominent. The blocky Ti-oxides, which have a strong effect on the mechanical properties before and after irradiation, were dissolved in the interface region of NIFS-HEAT-2. Understanding the effect of heat treatment (namely, post-coating heat treatment) on W-coated materials is important to reduce the irradiation induced hardening effects on the materials. After a heat load of about 5 MW/m2 (∼16 cycles), the surface of VPS-W has a very fine rough structure but no prominent cracks due to thermal heat loads were detected.

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 SUPPL.1

ER -

Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti

Abstract

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