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/
Files
Additional details
Identifiers
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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 33000738
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED CONTROL SYSTEMS; DOUBLET-3 DEVICE; ELECTRICAL FAULTS; EQUIPMENT PROTECTION DEVICES; HIGH-FREQUENCY DISCHARGES; ON-LINE MEASUREMENT SYSTEMS; PLASMA DIAGNOSTICS; PLASMA PRODUCTION
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONTROL SYSTEMS; ELECTRIC DISCHARGES; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Contract/Grant/Project number
- AC03-99ER54463
- Funding organization
- US Department of Energy (United States)