Published November 1, 1999 | Version v1
Report Restricted

Automated Fault Detection for DIII-D Tokamak Experiments

Description

An automated fault detection software system has been developed and was used during 1999 DIII-D plasma operations. The Fault Identification and Communication System (FICS) executes automatically after every plasma discharge to check dozens of subsystems for proper operation and communicates the test results to the tokamak operator. This system is now used routinely during DIII-D operations and has led to an increase in tokamak productivity

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00766648; PURL: https://www.osti.gov/servlets/purl/766648-jwqX9A/webviewable/

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
GA-A--23246

Conference

Title
18. IEEE/NPSS Symposium on Fusion Engineering
Dates
25-29 Oct 1999
Place
Albuquerque, NM (United States)

Optional Information

Contract/Grant/Project number
AC03-99ER54463
Funding organization
US Department of Energy (United States)