Materials erosion and redeposition studies at the PISCES-facility: net erosion under redeposition
Conference
·
OSTI ID:5569379
Simultaneous erosion and redeposition of copper and 304 stainless steel under controlled and continuous plasma (D,He,Ar) bombardment has been investigated in the PISCES-facility, which generates typical edge-plasma conditions of magnetic fusion devices. The plasma bombardment conditions are: incident ion flux in the range from 10/sup 17/ to 10/sup 18/ ions/sec/cm/sup 2/, ion bombarding energy of 100 eV, electron temperature in the range from 5 to 15 eV, plasma density in the range from 10/sup 11/ to 10/sup 13/ cm/sup -3/, target temperature in the range from 300 to 900K, and the total ion fluence in the range from 10/sup 20/ to 10/sup 22/ ions/cm/sup 2/. The net erosion yield under redeposition is found to be significantly smaller than the classical sputtering yield data. A first-order modeling is attempted to interpret the erosion and redeposition behavior of materials under plasma bombardment. It is pointed out both theoretically and experimentally that the mean free path for electron impact ionization of the sputtered material is the key parameter to control the overall mechanism of erosion and redeposition. Strongly modified surface morphologies of bombarded targets are observed and indicate a retrapping effect.
- Research Organization:
- California Univ., Los Angeles (USA). Dept. of Mechanical, Aerospace and Nuclear Engineering
- DOE Contract Number:
- AS03-84ER52104
- OSTI ID:
- 5569379
- Report Number(s):
- UCLA/PPG-980; CONF-860421-49; ON: DE86010867
- Country of Publication:
- United States
- Language:
- English
Similar Records
Erosion and redeposition experiments in the PISCES facility
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Technical Report
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Thu May 01 00:00:00 EDT 1986
·
OSTI ID:5271724
Materials surface modification by plasma bombardment under simultaneous erosion and redeposition conditions
Conference
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Tue Jul 01 00:00:00 EDT 1986
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OSTI ID:5308159
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Conference
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Mon Aug 01 00:00:00 EDT 1988
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OSTI ID:6821445
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COPPER
CORROSION RESISTANT ALLOYS
ELEMENTS
EROSION
FIRST WALL
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INTERACTIONS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
METALS
NICKEL ALLOYS
PLASMA
PLASMA SHEATH
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
TRANSITION ELEMENTS
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COPPER
CORROSION RESISTANT ALLOYS
ELEMENTS
EROSION
FIRST WALL
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INTERACTIONS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
METALS
NICKEL ALLOYS
PLASMA
PLASMA SHEATH
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
TRANSITION ELEMENTS