Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation

F. L. Chong; J. L. Chen; J. G. Li

doi:10.1016/j.jnucmat.2007.01.194

Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation

F. L. Chong
, J. L. Chen
, J. G. Li

School of Electrical Engineering

CAS - Institute of Plasma Physics

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

40 Scopus citations

Abstract

VPS-W coatings on CuCrZr with W/Cu interlayer and powder metallurgic W/Cu functionally graded material (FGM) were tested under high heat flux with active cooling and plasma irradiation in the HT-7 device. Results showed that after 10 MW/m² thermal shock experiment, exfoliation and crack appeared, however, the interface was not damaged except a few pores. VPS-W can withstand 150 cycles for 100s pulses under 6 MW/m². After plasma irradiation, tungsten carbide and tungsten oxide were observed by XPS analysis. Bubbles were observed on the surface of W/Cu FGM. These indicated that VPS-W coatings on CuCrZr with W/Cu interlayer have good thermal performance, and W/Cu interlayer was a better alternative compliant layer which can realize reliable W/CuCrZr joint, and the pore microstructure of VPS-W coating is helpful to inhibit the bubble formation.

Original language	English
Pages (from-to)	1201-1205
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	363-365
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2007.01.194
State	Published - 15 Jun 2007

Keywords

Electron beam irradiation
HT-7
Plasma facing material
Tungsten

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10.1016/j.jnucmat.2007.01.194

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title = "Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation",

abstract = "VPS-W coatings on CuCrZr with W/Cu interlayer and powder metallurgic W/Cu functionally graded material (FGM) were tested under high heat flux with active cooling and plasma irradiation in the HT-7 device. Results showed that after 10 MW/m2 thermal shock experiment, exfoliation and crack appeared, however, the interface was not damaged except a few pores. VPS-W can withstand 150 cycles for 100s pulses under 6 MW/m2. After plasma irradiation, tungsten carbide and tungsten oxide were observed by XPS analysis. Bubbles were observed on the surface of W/Cu FGM. These indicated that VPS-W coatings on CuCrZr with W/Cu interlayer have good thermal performance, and W/Cu interlayer was a better alternative compliant layer which can realize reliable W/CuCrZr joint, and the pore microstructure of VPS-W coating is helpful to inhibit the bubble formation.",

keywords = "Electron beam irradiation, HT-7, Plasma facing material, Tungsten",

author = "Chong, \{F. L.\} and Chen, \{J. L.\} and Li, \{J. G.\}",

year = "2007",

month = jun,

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doi = "10.1016/j.jnucmat.2007.01.194",

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journal = "Journal of Nuclear Materials",

issn = "0022-3115",

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TY - JOUR

T1 - Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation

AU - Chong, F. L.

AU - Chen, J. L.

AU - Li, J. G.

PY - 2007/6/15

Y1 - 2007/6/15

N2 - VPS-W coatings on CuCrZr with W/Cu interlayer and powder metallurgic W/Cu functionally graded material (FGM) were tested under high heat flux with active cooling and plasma irradiation in the HT-7 device. Results showed that after 10 MW/m2 thermal shock experiment, exfoliation and crack appeared, however, the interface was not damaged except a few pores. VPS-W can withstand 150 cycles for 100s pulses under 6 MW/m2. After plasma irradiation, tungsten carbide and tungsten oxide were observed by XPS analysis. Bubbles were observed on the surface of W/Cu FGM. These indicated that VPS-W coatings on CuCrZr with W/Cu interlayer have good thermal performance, and W/Cu interlayer was a better alternative compliant layer which can realize reliable W/CuCrZr joint, and the pore microstructure of VPS-W coating is helpful to inhibit the bubble formation.

AB - VPS-W coatings on CuCrZr with W/Cu interlayer and powder metallurgic W/Cu functionally graded material (FGM) were tested under high heat flux with active cooling and plasma irradiation in the HT-7 device. Results showed that after 10 MW/m2 thermal shock experiment, exfoliation and crack appeared, however, the interface was not damaged except a few pores. VPS-W can withstand 150 cycles for 100s pulses under 6 MW/m2. After plasma irradiation, tungsten carbide and tungsten oxide were observed by XPS analysis. Bubbles were observed on the surface of W/Cu FGM. These indicated that VPS-W coatings on CuCrZr with W/Cu interlayer have good thermal performance, and W/Cu interlayer was a better alternative compliant layer which can realize reliable W/CuCrZr joint, and the pore microstructure of VPS-W coating is helpful to inhibit the bubble formation.

KW - Electron beam irradiation

KW - HT-7

KW - Plasma facing material

KW - Tungsten

UR - https://www.scopus.com/pages/publications/34248580691

U2 - 10.1016/j.jnucmat.2007.01.194

DO - 10.1016/j.jnucmat.2007.01.194

M3 - 文章

AN - SCOPUS:34248580691

SN - 0022-3115

VL - 363-365

SP - 1201

EP - 1205

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation

Abstract

Keywords

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