Published December 1979 | Version v1
Journal article

Surface damage and sputtering of ATJ graphite as candidate armor plate material for TFTR under D+ bombardment

  • 1. Argonne National Lab., IL (USA)
  • 2. Princeton Univ., NJ (USA). Plasma Physics Lab.

Description

Experiments have been conducted to determine surface damage and total sputtering yields of ATJ graphite (a candidate armor plate material) caused by D+ ion irradiation at 40-, 60-, and 120- keV for fluxes close to those expected to reach the armor plate during the operation of neutral beam injectors used for the Tokamak Fusion Test Reactor (TFTR). The irradiations for surface damage studies were conducted both in the pulsed mode and in the continuous mode. Scanning electron microscopy of irradiated surfaces revealed surface damage in the form of ridges and grooves for both pulsed and continuous irradiation. Total sputtering yields for ATJ graphite samples which reached surface temperatures characteristic for given beam power depositions are given for 40-, 60-, and 120-keV D+ irradiations at normal incidence. (orig.)

Additional details

Publishing Information

Journal Title
J. Nucl. Mater.
Journal Volume
85-86
Journal Issue
pt.A
Series
J. Nucl. Mater.
Journal Page Range
225-230
ISSN
0022-3115

Conference

Title
1. topical meeting on fusion reactor materials.
Dates
29 - 31 Jan 1979.
Place
Miami Beach, FL.