Forensic Analysis of Faulted NSTX-U Inner Poloidal Field Coil
- 1. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Description
The failure of the NSTX-U PF1A upper coil suspended plasma operations during the project's first operational campaign after commissioning. Initial nondestructive testing and examination of the failed coil was followed by extensive nondestructive radiography. Destructive testing facilitated visual borescope/videoscope inspection through the cooling path, vacuum testing, and electrical testing of every conductor segment. One conductor cooling path visually evidenced a void through the sidewall of the cooling path in a layer-to-layer region. The identified void in the conductor cooling path was not proximal to a braze or joggle. Electrical testing indicated that the voided conductor segment was a member of a group of 14 conductor segments that evidenced low-resistance connectivity. Four braze joints and two lead segments were subjected to 400-lbf/in 2 hydrostatic pressure testing followed by helium leak testing and evidenced that there were no detectable leaks in the tested cooling path segments. The faulted region was proximal to the center of the coil pack and evidenced historical electrical pitting and molten conductor debris. Samples of the epoxy resin insulation system were extracted and analyzed with dynamic mechanical analysis and differential scanning calorimetry techniques. Epoxy resin insulation samples were subjected to immersion testing per ASTM D570. Metallurgical samples were extracted from the coil pack conductors and subjected to hardness testing and grain structure analysis. The base material testing results indicated no abnormalities. In conclusion, the coil incipient failure was determined to most likely have resulted from conductive material located between conductor and insulation layers.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1463233; https://www.osti.gov/biblio/1463233; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo periodAdditional details
Additional titles
- Augmented title (English)
- KEYWORDS: COILS; MAGNETIC CONFINEMENT; MAINTENANCE; TOKAMAKS; CONDUCTORS; TESTING; PLASMAS; COOLANTS; TOROIDAL MAGNETIC FIELDS; CURRENT MEASUREMENT
Identifiers
Publishing Information
- Journal Title
- IEEE Transactions on Plasma Science
- Journal Volume
- 46
- Journal Issue
- 7
- Journal Page Range
- p. 2653-2662
- ISSN
- 0093-3813
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 51031720
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S42: ENGINEERING;
- Descriptors DEI
- DESTRUCTIVE TESTING; ELECTRICAL TESTING; EPOXIDES; FAILURES; LEAK TESTING; MAGNETIC CONFINEMENT; MAGNETIC FIELDS; MAINTENANCE; NSTX DEVICE; NUCLEAR FORENSICS; PLASMA; RESINS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; CRIME DETECTION; DETECTION; MATERIALS TESTING; NONDESTRUCTIVE TESTING; ORGANIC COMPOUNDS; ORGANIC OXYGEN COMPOUNDS; ORGANIC POLYMERS; PETROCHEMICALS; PETROLEUM PRODUCTS; PLASMA CONFINEMENT; POLYMERS; SPHEROMAK DEVICES; TESTING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Contract/Grant/Project number
- AC02-09CH11466
- Funding organization
- USDOE Office of Science - SC, Fusion Energy Sciences (FES) (SC-24) (United States)
- Secondary number(s)
- OSTIID--1463233