Performance of the INTOR poloidal divertor
Description
The next generation of large tokamak experiments is expected to have large particle and heat outfluxes (approx. 1023 particles/sec and 80 MW). These outfluxes must be controlled to provide adequate pumping of the helium ash and to minimize the sputtering erosion of the vacuum vessel walls, limiters, and neutralizer plates. A poloidal divertor design to solve these problems for INTOR has been done using a two-dimensional code which models the plasma as a fluid and solves equations for the flow of particles, momentum and energy, and calculates the neutral gas transport with Monte-Carlo techniques. These calculations show that there is a regime of operation where the density in the divertor is high and the temperature is low, thus easing the heat load and erosion problems. The neutral pressure at the plate is high, resulting in high gas throughputs, with modest pumping speeds
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
13662831.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- PPPL--1835
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13662831
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- EROSION; FIRST WALL; HELIUM; IMPURITIES; INTOR TOKAMAK; LIMITERS; PERFORMANCE; POLOIDAL FIELD DIVERTORS; SEPARATION PROCESSES; SPUTTERING; TWO-DIMENSIONAL CALCULATIONS; VACUUM SYSTEMS
- Descriptors DEC
- CLOSED PLASMA DEVICES; DIVERTORS; ELEMENTS; NONMETALS; RARE GASES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES