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PFPO plasma scenarios for exploration of long pulse operation in ITER

Journal Article · · Nuclear Fusion
 [1];  [1];  [2];  [1];  [3];  [2];  [1];  [1];  [4];  [5];  [6];  [1];  [6];  [6];  [1]
  1. International Thermonuclear Experimental Reactor Organization (ITER) (France)
  2. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
  3. Keldysh Institution of Applied Mathematics (Russian Federation)
  4. JSC D.V. Efremov Institute of Electrophysical Apparatus (NIIEFA) (Russian Federation)
  5. Laboratory for Plasma Physics of the Ecole Royale Militaire (LPP-ERM) (Belgium)
  6. National Research Centre, Moscow (Russian Federation). Kurchatov Institute
Long Pulse Scenarios (LPS) in ITER foreseen during the Pre-Fusion Power Operation (PFPO) phase of the ITER Research Plan (IRP) are assessed using 1.5D transport simulations within the ASTRA framework. Such assessment is required to predict the operational space for LPS operation in PFPO, as well as to evaluate which physics processes for LPS operation during Fusion Power Operation (FPO) could be studied during PFPO. An important aspect in the development of LPSs in PFPO is to minimize lifetime consumption of the Central Solenoid (CS) for these scenarios. The maximum pulse length achievable for LPSs in PFPO with no consumption of CS lifetime (currents in CS coils $⩽$30 kA per turn) has been assessed for a range of heating schemes and heating mixes, confinement regimes (L-mode and H-mode) and for helium and hydrogen plasmas. The operational space of LPS and pulse length has been explored through density scans with the Heating and Current Drive mix required for the FPO Q $⩾$ 5 steady-state plasma scenario (namely Neutral Beam Injection and Electron Cyclotron Heating) including acceptable shine through losses on the first wall for both helium and hydrogen plasmas. Fast particle physics aspects that are common between FPO plasmas and LPS PFPO H-mode plasmas at low densities are studied including MHD stability analysis with the KINX code and non-perturbative critical gradient model based on high-n Toroidal Alfven Eigenmodes (TAE) stability kinetic ballooning code HINST calculations.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1986330
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 7 Vol. 63; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (36)

Studies of Plasma Equilibrium and Transport in a Tokamak Fusion Device with the Inverse-Variable Technique journal December 1993
The KINX ideal MHD stability code for axisymmetric plasmas with separatrix journal June 1997
Status of ITER journal November 2002
Impurity seeding in ITER DT plasmas in a carbon-free environment journal August 2015
Enhanced performance in fusion plasmas through turbulence suppression by megaelectronvolt ions journal June 2022
ICRF heating schemes for the ITER non-active phase journal January 2017
Trapped electron stabilization of ballooning modes in low aspect ratio toroidal plasmas journal October 2004
1.5D quasilinear model and its application on beams interacting with Alfvén eigenmodes in DIII-D journal September 2012
Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITERa) journal May 2015
Isotope and fast ions turbulence suppression effects: Consequences for high-β ITER plasmas journal May 2018
Physics and applications of three-ion ICRF scenarios for fusion research journal February 2021
Prediction of the energetic particle redistribution by an improved critical gradient model and analysis of the transport threshold journal March 2022
ITER L mode confinement database journal September 1997
Scaling of rotation and momentum confinement in JET plasmas journal April 2008
Simulations of combined neutral beam injection and ion cyclotron heating with the TORIC-SSFPQL package journal September 2011
Assessment of plasma parameters for the low activation phase of ITER operation journal November 2013
Development of advanced inductive scenarios for ITER journal December 2013
Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition journal May 2014
Assessment of operational space for long-pulse scenarios in ITER journal May 2015
Validating predictive models for fast ion profile relaxation in burning plasmas journal July 2016
CORSICA modelling of ITER hybrid operation scenarios journal August 2016
Hybrid advanced scenarios: perspectives for ITER and new experiments with dominant RF heating journal November 2004
Heating neutral beams for ITER: negative ion sources to tune fusion plasmas journal May 2017
Modelling of transitions between L- and H-mode in JET high plasma current plasmas and application to ITER scenarios including tungsten behaviour journal June 2017
Development of ITER non-activation phase operation scenarios journal June 2017
Isotope identity experiments in JET-ILW with H and D L-mode plasmas journal June 2019
The role of the source versus the collisionality in predicting a reactor density profile as observed on ASDEX Upgrade discharges journal June 2019
Modelling one-third field operation in the ITER pre-fusion power operation phase journal September 2019
Reassessment of steady-state operation in ITER with NBI and EC heating and current drive journal August 2020
A study of the heating and current drive options and confinement requirements to access steady-state plasmas at Q ∼ 5 in ITER and associated operational scenario development journal May 2021
Impact of suprathermal ions on neutron yield in the pre-DT phase of ITER operation journal June 2021
H-mode plasmas in the pre-fusion power operation 1 phase of the ITER research plan journal June 2021
Simulation of heating and current drive sources for scenarios of the ITER research plan journal November 2021
The power threshold of H-mode access in mixed hydrogen–tritium and pure tritium plasmas at JET with ITER-like wall journal May 2022
Multi-scale analysis of global electromagnetic instabilities in ITER pre-fusion-power operation plasmas journal September 2022
Power requirement for accessing the H-mode in ITER journal July 2008

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