Time-to-burnout data for a prototypical ITER divertor tube during a simulated loss of flow accident
Creators
- 1. Rensselaer Polytechnic Inst., Troy, NY (United States)
- 2. Sandia National Labs., Albuquerque, NM (United States)
- 3. Idaho National Engineering Lab., Idaho Falls, ID (United States)
Description
The Loss of Flow Accident (LOFA) is a serious safety concern for the International Thermonuclear Experimental Reactor (ITER) as it has been suggested that greater than 100 seconds are necessary to safely shutdown the plasma when ITER is operating at full power. In this experiment, the thermal response of a prototypical ITER divertor tube during a simulated LOFA was studied. The divertor tube was fabricated from oxygen-free high-conductivity copper to have a square geometry with a circular coolant channel. The coolant channel inner diameter was 0.77 cm, the heated length was 4.0 cm, and the heated width was 1.6 cm. The mockup did not feature any flow enhancement techniques, i.e., swirl tape, helical coils, or internal fins. One-sided surface heating of the mockup was accomplished through the use of the 30 kW Sandia Electron Beam Test System. After reaching steady state temperatures in the mockup, as determined by two Type-K thermocouples installed 0.5 mm beneath the heated surface, the coolant pump was manually tripped off and the coolant flow allowed to naturally coast down. Electron beam heating continued after the pump trip until the divertor tube's heated surface exhibited the high temperature transient normally indicative of rapidly approaching burnout. Experimental data showed that time-to-burnout increases proportionally with increasing inlet velocity and decreases proportionally with increasing incident heat flux
Additional details
Publishing Information
- Publisher
- Institute of Electrical and Electronics Engineers, Inc.
- Imprint Place
- Piscataway, NJ (United States)
- ISBN
- 0-7803-2970-8
- Imprint Title
- 1995 IEEE 16. symposium on fusion engineering. Volume 1
- Imprint Pagination
- 886 p.
- Journal Page Range
- p. 228-231.
Conference
- Title
- 16. IEEE/NPSS symposium on fusion engineering - seeking a new energy ERA (Sofe 95).
- Dates
- 1-5 Oct 1995.
- Place
- Champaign, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28070205
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACCIDENTS; BURNOUT; DIVERTORS; EXPERIMENTAL DATA; FLOW BLOCKAGE; HEAT TRANSFER; ITER TOKAMAK; THERMONUCLEAR REACTOR COOLING SYSTEMS
- Descriptors DEC
- CLOSED PLASMA DEVICES; COOLING SYSTEMS; DATA; ENERGY TRANSFER; INFORMATION; NUMERICAL DATA; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-950905--.