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Title: The ITPA disruption database

Abstract

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.

Authors:
 [1];  [2];  [3];  [4];  [5];  [6];  [7];  [8];  [9];  [8]
  1. General Atomics, San Diego, CA (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
  4. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
  5. ITER Organization, St. Paul Lez Durance (France)
  6. Swiss Federal Institute of Technology, Lausanne (Switzlerland). Plasma Physics Research Center
  7. Max Planck Inst. for Plasma Physics, Garching (Germany)
  8. Culham Centre for Fusion Energy (CCFE), Abingdon (United Kingdom). Culham Science Centre
  9. Inst. for Plasma Research, Gandhinagar (India)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Contributing Org.:
The ITPA Disruption Database Participants
OSTI Identifier:
1371725
Grant/Contract Number:  
FC02-04ER54698; FC02-99ER54512-CMOD; AC02-09CH11466
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 55; Journal Issue: 6; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; magnetic confinement; equilibrium; tokamaks

Citation Formats

Eidietis, N. W., Gerhardt, S. P., Granetz, R. S., Kawano, Y., Lehnen, M., Lister, J. B., Pautasso, G., Riccardo, V., Tanna, R. L., and Thornton, A. J. The ITPA disruption database. United States: N. p., 2015. Web. doi:10.1088/0029-5515/55/6/063030.
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. The ITPA disruption database. United States. https://doi.org/10.1088/0029-5515/55/6/063030
Eidietis, N. W., Gerhardt, S. P., Granetz, R. S., Kawano, Y., Lehnen, M., Lister, J. B., Pautasso, G., Riccardo, V., Tanna, R. L., and Thornton, A. J. 2015. "The ITPA disruption database". United States. https://doi.org/10.1088/0029-5515/55/6/063030. https://www.osti.gov/servlets/purl/1371725.
@article{osti_1371725,
title = {The ITPA disruption database},
author = {Eidietis, N. W. and Gerhardt, S. P. and Granetz, R. S. and Kawano, Y. and Lehnen, M. and Lister, J. B. and Pautasso, G. and Riccardo, V. and Tanna, R. L. and Thornton, A. J.},
abstractNote = {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.},
doi = {10.1088/0029-5515/55/6/063030},
url = {https://www.osti.gov/biblio/1371725}, journal = {Nuclear Fusion},
issn = {0029-5515},
number = 6,
volume = 55,
place = {United States},
year = {Fri May 22 00:00:00 EDT 2015},
month = {Fri May 22 00:00:00 EDT 2015}
}

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Works referenced in this record:

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Works referencing / citing this record:

Modeling of rapid shutdown in the DIII-D tokamak by core deposition of high-Z material
journal, June 2017


Local and integral disruption forces on the tokamak wall
journal, March 2018


On the design and role of passive stabilisation within the ST40 spherical tokamak
journal, April 2018


Kink instabilities of the post-disruption runaway electron beam at low safety factor
journal, March 2019


Tokamak research at the Ioffe Institute
journal, August 2019


Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond
journal, August 2019


Smaller and quicker with spherical tokamaks and high-temperature superconductors
journal, February 2019