Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma
Creators
- 1. Consorzio RFX Padova (Italy)
- 2. Dipartimento di Ingegneria Industriale, Università di Padova, Padova (Italy)
Description
The externally applied loop voltage, required to drive current carrying magnetic configurations, such as tokamaks or reversed field pinches (RFP), can induce currents between the plasma and the surrounding conducting components, such as limiters, divertor sections, stabilizing plates or enclosing stabilizing shells with insulated electrical gaps. An appropriate modeling of this problem can quantify these currents and give constraints for the design of new devices. In this paper a methodology based on lumped element circuit is used to evaluate this problem for the case of in vessel components of the RFX-mod2, which led to a redesign of the electrical connections of plasma facing components. In the new design some parts, having applied potential in the kV range, are still exposed to the weakly ionized scrape off plasma. The process of arc formation between them and their prevention had been experimentally investigated and possible arc suppression strategies identified.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2018.04.103Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2018.04.103;
- PII
- S0920379618303971;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 136
- Journal Issue
- Part B
- Journal Page Range
- p. 1209-1213
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51017616
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CONTAINERS; DESIGN; DIVERTORS; ELECTRIC POTENTIAL; FIRST WALL; LIMITERS; LIMITING VALUES; MAGNETIC FIELDS; PLASMA; PLATES; REVERSED-FIELD PINCH DEVICES; REVERSE-FIELD PINCH; SIMULATION; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; PINCH DEVICES; PINCH EFFECT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOROIDAL PINCH DEVICES
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.