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The ITER poloidal field system

Abstract

The ITER poloidal field (PF) system uses superconducting coils to provide the plasma equilibrium fields, slow equilibrium control and plasma flux linkage (V-s) needed for the ITER Operations and Research Program. Double-null (DN) divertor plasmas and operation scenarios for 22 MA Physics (high-Q/ignition) and 15 MA Technology (high-fluence testing) phases are provided. For 22 MA plasmas, total PF flux swing is 333 V-s. This provides inductive current drive (CD) for start-up with 66 V-s of resistive loss and 440-s (330-s minimum) sustained burn. The PF system also allows plasma start-up and shutdown scenarios, and can maintain the plasma configuration during burn over a range of current and pressure profiles. Other capabilities include increased plasma current (25 MA with inductive CD; 28 MA with non-inductive CD assist), divertor separatrix sweeping, and semi-DN and single-null plasmas.
Authors:
Wesley, J; [1]  Beljakov, V; Kavin, A; Korshakov, V; Kostenko, A; Roshal, A; Zakharov, L; [2]  Bulmer, R; Kaiser, T; Miller, J R; Pearlstein, L D; [3]  Hogan, J; [4]  Kurihara, K; Shimomura, Y; Sugihara, M; Yoshino, R [5] 
  1. General Atomics, San Diego, CA (USA)
  2. Kurchatov Inst. of Atomic Energy, Moscow (USSR)
  3. Lawrence Livermore National Lab., CA (USA)
  4. Oak Ridge National Lab., TN (USA)
  5. Japan Atomic Energy Resea
Publication Date:
Dec 15, 1990
Product Type:
Conference
Report Number:
IAEA-CN-53/F-3-16; CONF-901025-25
Reference Number:
EDB-90-183332; ERA-16-003367
Resource Relation:
Conference: 13. international conference on plasma physics and controlled nuclear fusion research, Washington, DC (USA), 1-6 Oct 1990
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; POLOIDAL FIELD DIVERTORS; DESIGN; ITER TOKAMAK; OPTIMIZATION; PERFORMANCE; CLOSED PLASMA DEVICES; DIVERTORS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; 700202* - Fusion Power Plant Technology- Magnet Coils & Fields
Sponsoring Organizations:
DOE/ER
OSTI ID:
6358065
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
Austria
Language:
English
Contract Number:
AC05-84OR21400
Other Identifying Numbers:
Other: ON: DE91002645
Availability:
NTIS, PC A02/MF A01 - OSTI; GPO Dep.
Submitting Site:
TIC
Size:
Pages: (6 p)
Announcement Date:
Dec 15, 1990

Citation Formats

Wesley, J, Beljakov, V, Kavin, A, Korshakov, V, Kostenko, A, Roshal, A, Zakharov, L, Bulmer, R, Kaiser, T, Miller, J R, Pearlstein, L D, Hogan, J, Kurihara, K, Shimomura, Y, Sugihara, M, and Yoshino, R. The ITER poloidal field system. Austria: N. p., 1990. Web.
Wesley, J, Beljakov, V, Kavin, A, Korshakov, V, Kostenko, A, Roshal, A, Zakharov, L, Bulmer, R, Kaiser, T, Miller, J R, Pearlstein, L D, Hogan, J, Kurihara, K, Shimomura, Y, Sugihara, M, & Yoshino, R. The ITER poloidal field system. Austria.
Wesley, J, Beljakov, V, Kavin, A, Korshakov, V, Kostenko, A, Roshal, A, Zakharov, L, Bulmer, R, Kaiser, T, Miller, J R, Pearlstein, L D, Hogan, J, Kurihara, K, Shimomura, Y, Sugihara, M, and Yoshino, R. 1990. "The ITER poloidal field system." Austria.
@misc{etde_6358065,
title = {The ITER poloidal field system}
author = {Wesley, J, Beljakov, V, Kavin, A, Korshakov, V, Kostenko, A, Roshal, A, Zakharov, L, Bulmer, R, Kaiser, T, Miller, J R, Pearlstein, L D, Hogan, J, Kurihara, K, Shimomura, Y, Sugihara, M, and Yoshino, R}
abstractNote = {The ITER poloidal field (PF) system uses superconducting coils to provide the plasma equilibrium fields, slow equilibrium control and plasma flux linkage (V-s) needed for the ITER Operations and Research Program. Double-null (DN) divertor plasmas and operation scenarios for 22 MA Physics (high-Q/ignition) and 15 MA Technology (high-fluence testing) phases are provided. For 22 MA plasmas, total PF flux swing is 333 V-s. This provides inductive current drive (CD) for start-up with 66 V-s of resistive loss and 440-s (330-s minimum) sustained burn. The PF system also allows plasma start-up and shutdown scenarios, and can maintain the plasma configuration during burn over a range of current and pressure profiles. Other capabilities include increased plasma current (25 MA with inductive CD; 28 MA with non-inductive CD assist), divertor separatrix sweeping, and semi-DN and single-null plasmas.}
place = {Austria}
year = {1990}
month = {Dec}
}