The ITPA disruption database

Eidietis, N. W.; Gerhardt, S. P.; Granetz, R. S.; Kawano, Y.; Lehnen, M.; Lister, J. B.; Pautasso, G.; Riccardo, V.; Tanna, R. L.; Thornton, A. J.

doi:10.1088/0029-5515/55/6/063030

Title: The ITPA disruption database

Journal Article · Fri May 22 00:00:00 EDT 2015 · Nuclear Fusion

DOI:https://doi.org/10.1088/0029-5515/55/6/063030· OSTI ID:1371725

Eidietis, N. W. ^[1]; Gerhardt, S. P. ^[2]; Granetz, R. S. ^[3]; Kawano, Y. ^[4]; Lehnen, M. ^[5]; Lister, J. B. ^[6]; Pautasso, G. ^[7]; Riccardo, V. ^[8]; Tanna, R. L. ^[9]; Thornton, A. J. ^[8]

General Atomics, San Diego, CA (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
ITER Organization, St. Paul Lez Durance (France)
Swiss Federal Institute of Technology, Lausanne (Switzlerland). Plasma Physics Research Center
Max Planck Inst. for Plasma Physics, Garching (Germany)
Culham Centre for Fusion Energy (CCFE), Abingdon (United Kingdom). Culham Science Centre
Inst. for Plasma Research, Gandhinagar (India)

A multi-device database of disruption characteristics has been developed under the auspices of the International Tokamak Physics Activity magneto hydrodynamics topical group. The purpose of this ITPA Disruption Database (IDDB) is to find the commonalities between the disruption and disruption mitigation characteristics in a wide variety of tokamaks in order to elucidate the physics underlying tokamak disruptions and to extrapolate toward much larger devices, such as ITER and future burning plasma devices. Conversely, in order to previous smaller disruption data collation efforts, the IDDB aims to provide significant context for each shot provided, allowing exploration of a wide array of relationships between pre-disruption and disruption parameters. Furthermore, the IDDB presently includes contributions from nine tokamaks, including both conventional aspect ratio and spherical tokamaks. An initial parametric analysis of the available data is presented. Our analysis includes current quench rates, halo current fraction and peaking, and the effectiveness of massive impurity injection. The IDDB is publicly available, with instruction for access provided herein.

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Research Organization:: General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Contributing Organization:: The ITPA Disruption Database Participants

Grant/Contract Number:: FC02-04ER54698; FC02-99ER54512-CMOD; AC02-09CH11466

OSTI ID:: 1371725

Journal Information:: Nuclear Fusion, Vol. 55, Issue 6; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 42 works

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