Published October 2010 | Version v1
Report

Disruption, Halo Current and Rapid Shutdown Database Activities for ITER

  • 1. General Atomics, PO Box 85608, San Diego, CA 92186-5608 (United States)
  • 2. FOM Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, PO Box 1207, 3430 BE Nieuwegein (Netherlands)
  • 3. Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543-0451 (United States)
  • 4. Massachusetts Institute of Technology, 77 Massachusetts Ave., Cambridge, MA 02139 (United States)
  • 5. ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France)
  • 6. Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom)
  • 7. University of California-San Diego, 9500 Gilman Dr., La Jolla, CA 92093 (United States)

Description

Full text: Disruption characterization and database development and analysis activities conducted for ITER under the aegis of the International Tokamak Physics Activity (ITPA) Topical Group on MHD Stability are described. An ITPA International Disruption Database (IDDB) Working Group and a MDSplus-based IDDB infrastructure for collection and retrieval of disruption-relevant tokamak data, first established in 2006, comprises one of the several 'joint experiments' being conducted by the MHD Topical Group. Analysis reported in 2006 of the current quench data from 7 elongated-plasma tokamaks provided a new recommendation about the lower bound on the plasma current decay time expected in ITER. In 2010, expansion of the scope and content of the IDDB to encompass halo current data has been initiated, and new combined current decay and halo current data sets (shot records) from the seven previously-contributing tokamaks are expected. The analysis to be reported in this paper will provide an 'integrated' current decay and halo current basis for updated recommendations to the ITER Organization in regard to ITER halo current magnitude and toroidal asymmetry and how these attributes correlate with the parent plasma aspect ratio, elongation and triangularity and current and toroidal field magnitudes. The feasibility of interpreting database composite and device-specific data in terms of a 'statistical' load severity spectrum will be explored. Activity has been initiated to add IDDB data categories for rapid plasma shutdowns effected by massive gas and pellet injection. This work was supported in part by the US Department of Energy under DE-FC02-04ER54698. (author)

Part of:
23. IAEA Fusion Energy Conference. Book of Abstracts

Additional details

Publishing Information

Imprint Title
23. IAEA Fusion Energy Conference. Book of Abstracts
Imprint Pagination
637 p.
Journal Page Range
p. 540-541
Report number
IAEA-CN--180

Conference

Title
23. IAEA Fusion Energy Conference
Acronym
FEC 2010
Dates
11-16 Oct 2010
Place
Daejeon (Korea, Republic of)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43046198
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ASPECT RATIO; ASYMMETRY; ELECTRIC CURRENTS; ELONGATION; ITER TOKAMAK; MAGNETOHYDRODYNAMICS; PELLET INJECTION; PLASMA; RECOMMENDATIONS
Descriptors DEC
CLOSED PLASMA DEVICES; CURRENTS; DEFORMATION; DIMENSIONLESS NUMBERS; FLUID MECHANICS; HYDRODYNAMICS; MECHANICS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Contract/Grant/Project number
Contract DE-FC02-04ER54698
Secondary number(s)
ITR--P1-26