Sputtering and surface damage of TFTR protective plate materials (Mo, TZM, graphite) by energetic D/sup +/ ion irradiation. Final report for Princeton Plasma Physics Laboratory
Studies have been conducted in accordance with a service request from the Plasma Physics Laboratory (PPPL) of Princeton University to determine the total sputtering yields and the surface damage of molybdenum (a candidate material for the neutral beam injector protective plate for Princeton's Fusion Test Reactor (TFTR)) caused by the impact of D/sup +/ ions at 120-keV, 60-keV and 40-keV at fluxes and total doses agreed upon between PPPL and ANL. The irradiations have been conducted in a specified pulsed mode as well as in a dc mode. The material TZM (a molybdenum alloy) was included in some tests of surface damage, but not for the full complement of doses planned for molybdenum. According to a request by PPPL the target temperature was not to be controlled (targets were allowed to reach a temperature determined by the beam power deposition and the conductive and radiative heat losses), but the target temperature was to be monitored. The irradiations were conducted at pressures ranging from 4 x 10/sup -9/ torr to 2 x 10/sup -8/ torr.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5004493
- Report Number(s):
- ANL/FPP/TM-105
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360106* -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-TZM
ALLOYS
CARBON
CHARGED PARTICLES
DEUTERIUM IONS
ELEMENTS
GRAPHITE
IONS
MATERIALS TESTING
METALS
MOLYBDENUM
MOLYBDENUM ALLOYS
MOLYBDENUM BASE ALLOYS
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REFRACTORY METALS
SHIELDING
TESTING
TFTR REACTORS
THERMONUCLEAR REACTORS
TITANIUM ALLOYS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
ZIRCONIUM ALLOYS