Bulletin of the American Physical Society
60th Annual Meeting of the APS Division of Plasma Physics
Volume 63, Number 11
Monday–Friday, November 5–9, 2018; Portland, Oregon
Session UP11: Poster Session VIII: MST; DIII-D Tokamak; SPARC, C-Mod, and High Field Tokamaks; HBT-EP; Transport and LPI in ICF Plasmas, Hydrodynamic Instability; HEDP Posters; Space and Astrophysical Plasmas (2:00pm-5:00pm)
Thursday, November 8, 2018
OCC
Room: Exhibit Hall A1&A
Abstract ID: BAPS.2018.DPP.UP11.50
Abstract: UP11.00050 : Integrated Simulations and Applications of Pellet Injection for Tokamak Central Fueling and Management of Transient Events**
Presenter:
Lang L Lao
(General Atomics)
Authors:
Lang L Lao
(General Atomics)
Yueqiang Liu
(General Atomics)
Brendan C Lyons
(General Atomics)
Joseph McClenaghan
(ORAU)
Orso Meneghini
(General Atomics)
Paul B Parks
(General Atomics)
Philip B Snyder
(General Atomics)
Wen Wu
(General Atomics)
Charlson C Kim
(SLS2 Consulting)
Vincent S Chan
(USTC, General Atomics)
Jiale Chen
(ASIPP)
Jiangang Li
(ASIPP)
Jie Zhang
(ASIPP)
Michael Lehnen
(ITER Organization)
Alberto Loarte
(ITER Organization)
Central fueling and management of transient events are critical tokamak research issues. Scoping studies using a new Pellet Ablation Module (PAM), developed based on an analytic ablation expression, and model density and temperature profiles, show that central fueling can be achieved for L-mode reactor plasmas, but would be challenging for H-mode reactor plasmas, as expected. Peak ablation location depends strongly on pellet injection velocity and size and central electron temperature. A PiC-based Shattered Pellet Injection (SPI) model has been developed to mimic the SPI fragment plume and implemented in the 3D MHD code NIMROD. DIII-D and ITER SPI simulations show that MHD mixing plays an important role in the dynamics of the thermal-quench event. NIMROD simulations with constant and temperature-dependent resistivity and thermal conduction show that the ITER baseline scenario is able to achieve full thermal quench with nearly 100% radiation with pure Ne or mixed Ne/D2 SPI. Detailed DIII-D and CFETR central-fueling simulations with self-consistent OMFIT core-pedestal workflows and DIII-D and ITER NIMROD SPI simulations will be presented.
**Work supported by US DOE under DE-FC02-04ER54698, DE-FG02-95ER54309, SciDAC DE-SC0018109 and DE-SC0016452, and GA ITER and CFETR Contracts.
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2018.DPP.UP11.50
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