ITER physics program and implications for plasma measurements
Creators
- Mukhovatov, V.1
- Costley, A.E.1
- Bartiromo, R.1
- Boucher, D.1
- Fujisawa, N.1
- Gribov, Y.1
- Janeschitz, G.1
- Johnson, L.1
- Kasai, S.1
- de Kock, L.1
- Marmar, E.1
- Muraoka, K.1
- Nagashima, A.1
- Orlinski, D.1
- Ortolani, S.1
- Perkins, F.1
- Petrov, M.1
- Post, D.1
- Putvinski, S.1
- Rosenbluth, M.1
- Sauter, O.1
- Stott, P.E.1
- Strelkov, V.1
- Vayakis, G.1
- Walker, C.1
- Wesley, J.C.1
- Yamamoto, S.1
- Young, K.M.1
- ITER Physics Expert Groups% ITER Joint Central Team and Home Teams
- 1. ITER San Diego Joint Work Site, La Jolla, California 92037 (United States)
Description
Key objectives of the first ten years of ITER operation are the investigation of the physics of burning plasmas and the demonstration of long-pulse ignited plasma technologies. These include studies of plasma confinement and stability, divertor operation, disruption mitigation and control, noninductive current drive, and steady state operation under conditions when the plasma is heated predominantly by alpha particles. The ITER operational plan envisages two and a half years for commissioning and initial operation with hydrogen plasmas at up to 100 MW of auxiliary heating power when initial tests of divertor operation and evaluation of disruption effects will be made. In order to meet the operational and programmatic goals, it will be necessary to make a wide range of plasma measurements. In this article the preliminary operational plan and physics program are presented and the implications for plasma measurements are outlined. copyright 1997 American Institute of Physics
Additional details
Publishing Information
- Journal Title
- Review of Scientific Instruments
- Journal Volume
- 68
- Journal Issue
- 2
- Journal Page Range
- p. 1250-1255.
- ISSN
- 0034-6748
- CODEN
- RSINAK
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28039627
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DIVERTORS; ITER TOKAMAK; MAGNETIC CONFINEMENT; OPERATION; PLASMA DIAGNOSTICS; PLASMA HEATING; PLASMA INSTABILITY; STABILITY
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; HEATING; INSTABILITY; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS