Development of compact tokamak fusion reactor use cases to inform future transport studies

Holland, C.; Bass, E. M.; Orlov, D. M.; McClenaghan, J.; Lyons, B. C.; Grierson, B. A.; Jian, X.; Howard, N. T.; Rodriguez-Fernandez, P.

doi:10.1017/S0022377823000843

Title: Development of compact tokamak fusion reactor use cases to inform future transport studies

Journal Article · 30 August 2023 · Journal of Plasma Physics

DOI: https://doi.org/10.1017/S0022377823000843 · OSTI ID:1997428

;

; McClenaghan, J.;

;

; Jian, X.; Howard, N. T.;

The OMFIT STEP (Meneghini et al. , Nucl. Fusion , vol. 10, 2020, p. 1088) workflow has been used to develop inductive and steady-state H-mode core plasma scenario use cases for a $$B_0 = 8 \, {\rm T}$$ , $$R_0 = 4 \, {\rm m}$$ machine to help guide and inform future higher-fidelity studies of core transport and confinement in compact tokamak reactors. Both use cases are designed to produce 200 MW or more of net electric power in an up-down symmetric plasma with minor radius $$a = 1.4 \, {\rm m}$$ , elongation $$\kappa = 2.0$$ , triangularity $$\delta = 0.5$$ and effective charge $$Z_{{\rm eff}} \simeq 2$$ . Additional considerations based on the need for compatibility of the core with reactor-relevant power exhaust solutions and external actuators were used to guide and constrain the use case development. An extensive characterization of core transport in both scenarios is presented, the most important feature of which is the extreme sensitivity of the results to the quantitative stiffness level of the transport model used as well as the predicted critical gradients. This sensitivity is shown to arise from different levels of transport stiffness exhibited by the models, combined with the gyroBohm-normalized fluxes of the predictions being an order of magnitude larger than other H-mode plasmas. Additionally, it is shown that although heating in both plasmas is predominantly to the electrons and collisionality is low, the plasmas remain sufficiently well coupled for the ions to carry a significant fraction of the thermal transport. As neoclassical transport is negligible in these conditions, this situation inherently requires long-wavelength ion gyroradius-scale turbulence to be the dominant transport mechanism in both plasmas. These results are combined with other basic considerations to propose a simple heuristic model of transport in reactor-relevant plasmas, along with simple metrics to quantify coupling and core transport properties across burning and non-burning plasmas.

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Research Organization:: General Atomics, San Diego, CA (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Univ. of California, Oakland, CA (United States); Univ. of California, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR). Scientific Discovery through Advanced Computing (SciDAC); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-05CH11231; FG02-95ER54309; SC0014264; SC0017992; SC0018287

OSTI ID:: 1997428

Journal Information:: Journal of Plasma Physics, Journal Name: Journal of Plasma Physics Journal Issue: 4 Vol. 89; ISSN 0022-3778

Publisher:: Cambridge University Press (CUP)Copyright Statement

Country of Publication:: United Kingdom

Language:: English

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Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors Pütterich, T.; Fable, E.; Dux, R. Nuclear Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1741-4326/ab0384	journal	March 2019
Progress toward ITER’s First Plasma Bigot, B. Nuclear Fusion, Vol. 59, Issue 11 https://doi.org/10.1088/1741-4326/ab0f84	journal	June 2019
The role of the source versus the collisionality in predicting a reactor density profile as observed on ASDEX Upgrade discharges Fable, E.; Angioni, C.; Bobkov, V. Nuclear Fusion, Vol. 59, Issue 7 https://doi.org/10.1088/1741-4326/ab1f28	journal	June 2019
Gyrokinetic analysis and simulation of pedestals to identify the culprits for energy losses using ‘fingerprints’ Kotschenreuther, M.; Liu, X.; Hatch, D. R. Nuclear Fusion, Vol. 59, Issue 9 https://doi.org/10.1088/1741-4326/ab1fa2	journal	July 2019
Predicting the rotation profile in ITER Chrystal, C.; Grierson, B. A.; Haskey, S. R. Nuclear Fusion, Vol. 60, Issue 3 https://doi.org/10.1088/1741-4326/ab6434	journal	January 2020
Integrated modeling of ASDEX Upgrade plasmas combining core, pedestal and scrape-off layer physics Luda, T.; Angioni, C.; Dunne, M. G. Nuclear Fusion, Vol. 60, Issue 3 https://doi.org/10.1088/1741-4326/ab6c77	journal	February 2020
Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges Eich, T.; Manz, P.; Goldston, R. J. Nuclear Fusion, Vol. 60, Issue 5 https://doi.org/10.1088/1741-4326/ab7a66	journal	April 2020
Neural-network accelerated coupled core-pedestal simulations with self-consistent transport of impurities and compatible with ITER IMAS Meneghini, O.; Snoep, G.; Lyons, B. C. Nuclear Fusion, Vol. 61, Issue 2 https://doi.org/10.1088/1741-4326/abb918	journal	December 2020
Impact of plasma density/collisionality on divertor heat flux width Li, N. M.; Xu, X. Q.; Goldston, R. J. Nuclear Fusion, Vol. 61, Issue 2 https://doi.org/10.1088/1741-4326/abc839	journal	December 2020
Steady state versus pulsed tokamak reactors Segal, D. J.; Cerfon, A. J.; Freidberg, J. P. Nuclear Fusion, Vol. 61, Issue 4 https://doi.org/10.1088/1741-4326/abe0d2	journal	March 2021
The advanced tokamak path to a compact net electric fusion pilot plant Buttery, R. J.; Park, J. M.; McClenaghan, J. T. Nuclear Fusion, Vol. 61, Issue 4 https://doi.org/10.1088/1741-4326/abe4af	journal	March 2021
The role of edge plasma parameters in H-mode density limit on the JET-ILW Sun, H. J.; Goldston, R. J.; Huber, A. Nuclear Fusion, Vol. 61, Issue 6 https://doi.org/10.1088/1741-4326/abf056	journal	April 2021
Examination of stiff ion temperature gradient mode physics in simulations of DIII-D H-mode transport Holland, C.; Luce, T. C.; Grierson, B. A. Nuclear Fusion, Vol. 61, Issue 6 https://doi.org/10.1088/1741-4326/abf951	journal	May 2021
Bounds on edge shear layer persistence while approaching the density limit Singh, Rameswar; Diamond, P. H. Nuclear Fusion, Vol. 61, Issue 7 https://doi.org/10.1088/1741-4326/abfadb	journal	June 2021
Benchmark of quasi-linear models against gyrokinetic single scale simulations in deuterium and tritium plasmas for a JET high beta hybrid discharge Mariani, A.; Mantica, P.; Casiraghi, I. Nuclear Fusion, Vol. 61, Issue 6 https://doi.org/10.1088/1741-4326/abfb12	journal	May 2021
The role of electron-scale turbulence in the JET tokamak: experiments and modelling Mantica, P.; Bonanomi, N.; Mariani, A. Nuclear Fusion, Vol. 61, Issue 9 https://doi.org/10.1088/1741-4326/ac146e	journal	August 2021
Overview of the SPARC physics basis towards the exploration of burning-plasma regimes in high-field, compact tokamaks Rodriguez-Fernandez, P.; Creely, A. J.; Greenwald, M. J. Nuclear Fusion, Vol. 62, Issue 4 https://doi.org/10.1088/1741-4326/ac1654	journal	March 2022
Preparing systems codes for power plant conceptual design Morris, J.; Coleman, M.; Kahn, S. Nuclear Fusion, Vol. 61, Issue 11 https://doi.org/10.1088/1741-4326/ac18dd	journal	September 2021
The role of ion and electron-scale turbulence in setting heat and particle transport in the DIII-D ITER baseline scenario Howard, N. T.; Holland, C.; Rhodes, T. L. Nuclear Fusion, Vol. 61, Issue 10 https://doi.org/10.1088/1741-4326/ac1bc2	journal	August 2021
Verification of a quasi-linear model for gyrokinetic turbulent transport Staebler, G. M.; Belli, E. A.; Candy, J. Nuclear Fusion, Vol. 61, Issue 11 https://doi.org/10.1088/1741-4326/ac243a	journal	September 2021
Simulation prediction of micro-instability transition and associated particle transport in tokamak plasmas Li, H.; Li, J. Q.; Fu, Y. L. Nuclear Fusion, Vol. 62, Issue 3 https://doi.org/10.1088/1741-4326/ac486b	journal	January 2022
Fusion pilot plant performance and the role of a sustained high power density tokamak Menard, J. E.; Grierson, B. A.; Brown, T. Nuclear Fusion, Vol. 62, Issue 3 https://doi.org/10.1088/1741-4326/ac49aa	journal	February 2022
Confinement properties of L-mode plasmas in ASDEX Upgrade and full-radius predictions of the TGLF transport model Angioni, C.; Gamot, T.; Tardini, G. Nuclear Fusion, Vol. 62, Issue 6 https://doi.org/10.1088/1741-4326/ac592b	journal	April 2022
Nonlinear gyrokinetic predictions of SPARC burning plasma profiles enabled by surrogate modeling Rodriguez-Fernandez, P.; Howard, N. T.; Candy, J. Nuclear Fusion, Vol. 62, Issue 7 https://doi.org/10.1088/1741-4326/ac64b2	journal	May 2022
Understanding the core confinement in DIII-D super-H experiments by transport modeling Jian, X.; Holland, C.; Ding, S. Nuclear Fusion, Vol. 62, Issue 8 https://doi.org/10.1088/1741-4326/ac71b5	journal	June 2022
Integrated modelling and multiscale gyrokinetic validation study of ETG turbulence in a JET hybrid H-mode scenario Citrin, J.; Maeyama, S.; Angioni, C. Nuclear Fusion, Vol. 62, Issue 8 https://doi.org/10.1088/1741-4326/ac7535	journal	June 2022
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Regulation of Alfvén Eigenmodes by Microturbulence in Fusion Plasmas Liu, P.; Wei, X.; Lin, Z. Physical Review Letters, Vol. 128, Issue 18 https://doi.org/10.1103/PhysRevLett.128.185001	journal	May 2022
First-Principles Density Limit Scaling in Tokamaks Based on Edge Turbulent Transport and Implications for ITER Giacomin, M.; Pau, A.; Ricci, P. Physical Review Letters, Vol. 128, Issue 18 https://doi.org/10.1103/PhysRevLett.128.185003	journal	May 2022
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