Fusion pilot plant performance and the role of a sustained high power density tokamak

Menard, J. E.; Grierson, B. A.; Brown, T.; Rana, C.; Zhai, Y.; Poli, F. M.; Maingi, R.; Guttenfelder, W.; Snyder, P. B.

doi:10.1088/1741-4326/ac49aa

Title: Fusion pilot plant performance and the role of a sustained high power density tokamak

Journal Article · 06 February 2022 · Nuclear Fusion

DOI: https://doi.org/10.1088/1741-4326/ac49aa · OSTI ID:1856193

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Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); General Atomics, San Diego, CA (United States)
General Atomics, San Diego, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Here, recent U.S. fusion development strategy reports all recommend that the U.S. should pursue innovative science and technology to enable construction of a fusion pilot plant (FPP) that produces net electricity from fusion at low capital cost. Compact tokamaks have been proposed as a means of potentially reducing the capital cost of a FPP. However, compact steady-state tokamak FPPs face the challenge of integrating a high fraction of self-driven current with high core confinement, plasma pressure, and high divertor parallel heat flux. This integration is sufficiently challenging that a dedicated sustained-high-power-density (SHPD) tokamak facility is proposed by the U.S. community as the optimal way to close this integration gap. Performance projections for the steady-state tokamak FPP regime are presented and a preliminary SHPD device with substantial flexibility in lower aspect ratio (A = 2–2.5), shaping, and divertor configuration to narrow gaps to an FPP is described.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Science (SC)

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 1856193

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 3 Vol. 62; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

References (116)

Fusion Pilot Plant performance and the role of a Sustained High Power Density tokamak Menard, Jonathan; Grierson, Brian; Brown, Tom Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/1888274	dataset	January 2022
Transp Breslau, Joshua; Gorelenkova, Marina; Poli, Francesca Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/dc.20180627.4	software	June 2018
Assessing ion–electron thermal equilibration in the scrape‐off layer of tokamaks using UEDGE Holm, A.; Groth, M.; Rognlien, T. D. Contributions to Plasma Physics, Vol. 58, Issue 6-8 https://doi.org/10.1002/ctpp.201700152	journal	April 2018
DIII-D Research to Prepare for Steady State Advanced Tokamak Power Plants Buttery, R. J.; Covele, B.; Ferron, J. Journal of Fusion Energy, Vol. 38, Issue 1 https://doi.org/10.1007/s10894-018-0185-y	journal	September 2018
Tolerance evaluation of poloidal shear keys for ITER TF coil Fu, Youkun; Cees, Jong; Neil, Mitchell Fusion Engineering and Design, Vol. 82, Issue 5-14 https://doi.org/10.1016/j.fusengdes.2007.02.019	journal	October 2007
The WEST project: PFC shaping solutions investigated for the ITER-like W divertor Missirlian, M.; Firdaouss, M.; Richou, M. Fusion Engineering and Design, Vol. 88, Issue 9-10 https://doi.org/10.1016/j.fusengdes.2013.03.048	journal	October 2013
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets Sorbom, B. N.; Ball, J.; Palmer, T. R. Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2015.07.008	journal	November 2015
Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy Kessel, C. E.; Blanchard, J. P.; Davis, A. Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.05.081	journal	October 2018
An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort Federici, G.; Boccaccini, L.; Cismondi, F. Fusion Engineering and Design, Vol. 141 https://doi.org/10.1016/j.fusengdes.2019.01.141	journal	April 2019
European DEMO first wall shaping and limiters design and analysis status Vizvary, Z.; Arter, W.; Bachmann, C. Fusion Engineering and Design, Vol. 158 https://doi.org/10.1016/j.fusengdes.2020.111676	journal	September 2020
The development of a Sustained High Power Density (SHPD) facility Brown, T.; Menard, J. E.; Zhai, Y. Fusion Engineering and Design, Vol. 168 https://doi.org/10.1016/j.fusengdes.2020.112214	journal	July 2021
DTT - Divertor Tokamak Test facility: A testbed for DEMO Ambrosino, R. Fusion Engineering and Design, Vol. 167 https://doi.org/10.1016/j.fusengdes.2021.112330	journal	June 2021
Divertor heat flux reduction and detachment experiments in NSTX Soukhanovskii, V. A.; Maingi, R.; Bush, C. E. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.075	journal	June 2007
Modelling of the ITER reference divertor plasma Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.10.083	journal	August 2011
MAST-upgrade divertor facility and assessing performance of long-legged divertors Fishpool, G.; Canik, J.; Cunningham, G. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.067	journal	July 2013
The new SOLPS-ITER code package Wiesen, S.; Reiter, D.; Kotov, V. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.10.012	journal	August 2015
Impurity seeding in ITER DT plasmas in a carbon-free environment Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.104	journal	August 2015
High heat flux limits of the fusion reactor water-cooled first wall Zacha, Pavel; Entler, Slavomir Nuclear Engineering and Technology, Vol. 51, Issue 5 https://doi.org/10.1016/j.net.2019.03.013	journal	August 2019
Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET Bernert, M.; Wischmeier, M.; Huber, A. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.12.029	journal	August 2017
Proposal of an alternative upper divertor in ASDEX Upgrade supported by EMC3-EIRENE simulations Lunt, T.; Zohm, H.; Herrmann, A. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.12.035	journal	August 2017
Investigations of the first-wall erosion of DEMO with the CELLSOR code Beckers, M.; Biel, W.; Tokar, M. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.01.006	journal	August 2017
Neutral pressure and separatrix density related models for seed impurity divertor radiation in ASDEX Upgrade Kallenbach, A.; Bernert, M.; Dux, R. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2018.12.021	journal	January 2019
Physics basis for the first ITER tungsten divertor Pitts, R. A.; Bonnin, X.; Escourbiac, F. Nuclear Materials and Energy, Vol. 20 https://doi.org/10.1016/j.nme.2019.100696	journal	August 2019
SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels Veselova, Irina; Kaveeva, Elizaveta; Rozhansky, Vladimir Nuclear Materials and Energy, Vol. 26 https://doi.org/10.1016/j.nme.2020.100870	journal	March 2021
Developments on two lithium vapor-box linear test-stand experiments Schwartz, Jacob A.; Goldston, R. J. Nuclear Materials and Energy, Vol. 26 https://doi.org/10.1016/j.nme.2021.100901	journal	March 2021
Modeling of liquid lithium flow in porous plasma facing material Khodak, Andrei; Maingi, Rajesh Nuclear Materials and Energy, Vol. 26 https://doi.org/10.1016/j.nme.2021.100935	journal	March 2021
Generalization of the Heuristic Drift SOL model for finite collisionality and effect on flow shearing rate vs. interchange growth rate Brown, A. O.; Goldston, R. J. Nuclear Materials and Energy, Vol. 27 https://doi.org/10.1016/j.nme.2021.101002	journal	June 2021
Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER Emdee, E. D.; Goldston, R. J.; Lore, J. D. Nuclear Materials and Energy, Vol. 27 https://doi.org/10.1016/j.nme.2021.101004	journal	June 2021
Overview of the SPARC tokamak Creely, A. J.; Greenwald, M. J.; Ballinger, S. B. Journal of Plasma Physics, Vol. 86, Issue 5 https://doi.org/10.1017/S0022377820001257	journal	September 2020
Real-time feedback control of the impurity emission front in tokamak divertor plasmas Ravensbergen, T.; van Berkel, M.; Perek, A. Nature Communications, Vol. 12, Issue 1 https://doi.org/10.1038/s41467-021-21268-3	journal	February 2021
Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas Wang, L.; Wang, H. Q.; Ding, S. Nature Communications, Vol. 12, Issue 1 https://doi.org/10.1038/s41467-021-21645-y	journal	March 2021
Top Launch for Higher Off-axis Electron Cyclotron Current Drive Efficiency Chen, Xi; Prater, Ron; Petty, Craig EPJ Web of Conferences, Vol. 203 https://doi.org/10.1051/epjconf/201920301004	journal	January 2019
Gyro-Landau fluid equations for trapped and passing particles Staebler, G. M.; Kinsey, J. E.; Waltz, R. E. Physics of Plasmas, Vol. 12, Issue 10 https://doi.org/10.1063/1.2044587	journal	October 2005
Sizing up plasmas using dimensionless parameters Petty, C. C. Physics of Plasmas, Vol. 15, Issue 8 https://doi.org/10.1063/1.2961043	journal	August 2008
High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) Q _DT = 10 operation Loarte, A.; Hughes, J. W.; Reinke, M. L. Physics of Plasmas, Vol. 18, Issue 5 https://doi.org/10.1063/1.3567547	journal	May 2011
Discovery of stationary operation of quiescent H-mode plasmas with net-zero neutral beam injection torque and high energy confinement on DIII-D Burrell, K. H.; Barada, K.; Chen, X. Physics of Plasmas, Vol. 23, Issue 5 https://doi.org/10.1063/1.4943521	journal	March 2016
Divertor plasma detachment Krasheninnikov, S. I.; Kukushkin, A. S.; Pshenov, A. A. Physics of Plasmas, Vol. 23, Issue 5 https://doi.org/10.1063/1.4948273	journal	May 2016
A fast low-to-high confinement mode bifurcation dynamics in the boundary-plasma gyrokinetic code XGC1 Ku, S.; Chang, C. S.; Hager, R. Physics of Plasmas, Vol. 25, Issue 5 https://doi.org/10.1063/1.5020792	journal	May 2018
Active spectroscopy measurements of the deuterium temperature, rotation, and density from the core to scrape off layer on the DIII-D tokamak (invited) Haskey, S. R.; Grierson, B. A.; Stagner, L. Review of Scientific Instruments, Vol. 89, Issue 10 https://doi.org/10.1063/1.5038349	journal	October 2018
Improved core-edge compatibility using impurity seeding in the small angle slot (SAS) divertor at DIII-D Casali, L.; Osborne, T. H.; Grierson, B. A. Physics of Plasmas, Vol. 27, Issue 6 https://doi.org/10.1063/1.5144693	journal	June 2020
A gyro-Landau-fluid transport model Waltz, R. E.; Staebler, G. M.; Dorland, W. Physics of Plasmas, Vol. 4, Issue 7 https://doi.org/10.1063/1.872228	journal	July 1997
Constructing a new predictive scaling formula for ITER's divertor heat-load width informed by a simulation-anchored machine learning Chang, C. S.; Ku, S.; Hager, R. Physics of Plasmas, Vol. 28, Issue 2 https://doi.org/10.1063/5.0027637	journal	February 2021
Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility Kessel, C. E.; Andruczyk, D.; Blanchard, J. P. Fusion Science and Technology, Vol. 75, Issue 8 https://doi.org/10.1080/15361055.2019.1610685	journal	June 2019
Cost Drivers for a Tokamak-Based Compact Pilot Plant Wade, M. R.; Leuer, J. A. Fusion Science and Technology, Vol. 77, Issue 2 https://doi.org/10.1080/15361055.2020.1858670	journal	February 2021
Concept Design and Analysis of the Magnet System of the Sustained High Power Density Tokamak Facility Rana, C.; Brown, T.; Titus, P. Fusion Science and Technology, Vol. 77, Issue 7-8 https://doi.org/10.1080/15361055.2021.1940645	journal	October 2021
Chapter 2: Plasma confinement and transport Transport, ITER Physics Expert Group on Confin; Database, ITER Physics Expert Group on Confin; Editors, ITER Physics Basis Nuclear Fusion, Vol. 39, Issue 12 https://doi.org/10.1088/0029-5515/39/12/302	journal	December 1999
Chapter 2: Plasma confinement and transport Physics), E. J. Doyle (Chair Transport; Modelling), W. A. Houlberg (Chair Confinement Da; Edge), Y. Kamada (Chair Pedestal and Nuclear Fusion, Vol. 47, Issue 6 https://doi.org/10.1088/0029-5515/47/6/S02	journal	June 2007
Chapter 1: Overview and summary Shimada, M.; Campbell, D. J.; Mukhovatov, V. Nuclear Fusion, Vol. 47, Issue 6 https://doi.org/10.1088/0029-5515/47/6/s01	journal	June 2007
SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid Tobita, K.; Nishio, S.; Sato, M. Nuclear Fusion, Vol. 47, Issue 8 https://doi.org/10.1088/0029-5515/47/8/022	journal	July 2007
Experimental vertical stability studies for ITER performance and design guidance Humphreys, D. A.; Casper, T. A.; Eidietis, N. Nuclear Fusion, Vol. 49, Issue 11 https://doi.org/10.1088/0029-5515/49/11/115003	journal	September 2009
Overview of L–H power threshold studies in NSTX Maingi, R.; Kaye, S. M.; Bell, R. E. Nuclear Fusion, Vol. 50, Issue 6 https://doi.org/10.1088/0029-5515/50/6/064010	journal	May 2010
A first-principles predictive model of the pedestal height and width: development, testing and ITER optimization with the EPED model Snyder, P. B.; Groebner, R. J.; Hughes, J. W. Nuclear Fusion, Vol. 51, Issue 10 https://doi.org/10.1088/0029-5515/51/10/103016	journal	August 2011
L–H threshold studies in NSTX Kaye, S. M.; Maingi, R.; Battaglia, D. Nuclear Fusion, Vol. 51, Issue 11 https://doi.org/10.1088/0029-5515/51/11/113019	journal	October 2011
Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks Goldston, R. J. Nuclear Fusion, Vol. 52, Issue 1 https://doi.org/10.1088/0029-5515/52/1/013009	journal	December 2011
Overview of the physics and engineering design of NSTX upgrade Menard, J. E.; Gerhardt, S.; Bell, M. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083015	journal	July 2012
Exploration of the equilibrium operating space for NSTX-Upgrade Gerhardt, S. P.; Andre, R.; Menard, J. E. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083020	journal	August 2012
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas Jaworski, M. A.; Abrams, T.; Allain, J. P. Nuclear Fusion, Vol. 53, Issue 8 https://doi.org/10.1088/0029-5515/53/8/083032	journal	July 2013
Progress in characterization of the pedestal stability and turbulence during the edge-localized-mode cycle on National Spherical Torus Experiment Diallo, A.; Canik, J.; Göerler, T. Nuclear Fusion, Vol. 53, Issue 9 https://doi.org/10.1088/0029-5515/53/9/093026	journal	August 2013
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER Eich, T.; Leonard, A. W.; Pitts, R. A. Nuclear Fusion, Vol. 53, Issue 9 https://doi.org/10.1088/0029-5515/53/9/093031	journal	August 2013
Parametric dependence of fast-ion transport events on the National Spherical Torus Experiment Fredrickson, E. D.; Gorelenkov, N. N.; Podesta, M. Nuclear Fusion, Vol. 54, Issue 9 https://doi.org/10.1088/0029-5515/54/9/093007	journal	August 2014
Overview of MAST results Chapman, I. T.; Adamek, J.; Akers, R. J. Nuclear Fusion, Vol. 55, Issue 10 https://doi.org/10.1088/0029-5515/55/10/104008	journal	June 2015
ADX: a high field, high power density, advanced divertor and RF tokamak LaBombard, B.; Marmar, E.; Irby, J. Nuclear Fusion, Vol. 55, Issue 5 https://doi.org/10.1088/0029-5515/55/5/053020	journal	April 2015
Design concept of K-DEMO for near-term implementation Kim, K.; Im, K.; Kim, H. C. Nuclear Fusion, Vol. 55, Issue 5 https://doi.org/10.1088/0029-5515/55/5/053027	journal	April 2015
Enhanced H-mode pedestals with lithium injection in DIII-D Osborne, T. H.; Jackson, G. L.; Yan, Z. Nuclear Fusion, Vol. 55, Issue 6 https://doi.org/10.1088/0029-5515/55/6/063018	journal	May 2015
Progress toward commissioning and plasma operation in NSTX-U Ono, M.; Chrzanowski, J.; Dudek, L. Nuclear Fusion, Vol. 55, Issue 7 https://doi.org/10.1088/0029-5515/55/7/073007	journal	June 2015
Integrated modeling applications for tokamak experiments with OMFIT Meneghini, O.; Smith, S. P.; Lao, L. L. Nuclear Fusion, Vol. 55, Issue 8 https://doi.org/10.1088/0029-5515/55/8/083008	journal	July 2015
Fusion nuclear science facilities and pilot plants based on the spherical tokamak Menard, J. E.; Brown, T.; El-Guebaly, L. Nuclear Fusion, Vol. 56, Issue 10 https://doi.org/10.1088/0029-5515/56/10/106023	journal	August 2016
Comparison of H-mode plasmas in JET-ILW and JET-C with and without nitrogen seeding Jaervinen, A. E.; Giroud, C.; Groth, M. Nuclear Fusion, Vol. 56, Issue 4 https://doi.org/10.1088/0029-5515/56/4/046012	journal	March 2016
Sensitivity of detachment extent to magnetic configuration and external parameters Lipschultz, Bruce; Parra, Felix I.; Hutchinson, Ian H. Nuclear Fusion, Vol. 56, Issue 5 https://doi.org/10.1088/0029-5515/56/5/056007	journal	April 2016
H-mode plasmas at very low aspect ratio on the Pegasus Toroidal Experiment Thome, K. E.; Bongard, M. W.; Barr, J. L. Nuclear Fusion, Vol. 57, Issue 2, Article No. 022018 https://doi.org/10.1088/0029-5515/57/2/022018	journal	September 2016
The lithium vapor box divertor Goldston, R. J.; Myers, R.; Schwartz, J. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/t167/1/014017	journal	January 2016
Density limits in toroidal plasmas Greenwald, Martin Plasma Physics and Controlled Fusion, Vol. 44, Issue 8 https://doi.org/10.1088/0741-3335/44/8/201	journal	July 2002
Roles of aspect ratio, absolute B and effective Z of the H-mode power threshold in tokamaks of the ITPA database Takizuka, ITPA H-mode Power Threshold Databas Plasma Physics and Controlled Fusion, Vol. 46, Issue 5A https://doi.org/10.1088/0741-3335/46/5a/024	journal	April 2004
Origin of the various beta dependences of ELMy H-mode confinement properties Takizuka, T.; Urano, H.; Takenaga, H. Plasma Physics and Controlled Fusion, Vol. 48, Issue 6 https://doi.org/10.1088/0741-3335/48/6/007	journal	May 2006
Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO Kallenbach, A.; Bernert, M.; Dux, R. Plasma Physics and Controlled Fusion, Vol. 55, Issue 12 https://doi.org/10.1088/0741-3335/55/12/124041	journal	November 2013
The effect of a metal wall on confinement in JET and ASDEX Upgrade Beurskens, M. N. A.; Schweinzer, J.; Angioni, C. Plasma Physics and Controlled Fusion, Vol. 55, Issue 12 https://doi.org/10.1088/0741-3335/55/12/124043	journal	November 2013
The H-mode density limit in the full tungsten ASDEX Upgrade tokamak Bernert, M.; Eich, T.; Kallenbach, A. Plasma Physics and Controlled Fusion, Vol. 57, Issue 1 https://doi.org/10.1088/0741-3335/57/1/014038	journal	November 2014
Analytical calculations for impurity seeded partially detached divertor conditions Kallenbach, A.; Bernert, M.; Dux, R. Plasma Physics and Controlled Fusion, Vol. 58, Issue 4 https://doi.org/10.1088/0741-3335/58/4/045013	journal	February 2016
A new scaling for divertor detachment Goldston, R. J.; Reinke, M. L.; Schwartz, J. A. Plasma Physics and Controlled Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1361-6587/aa5e6e	journal	March 2017
Managing leading edges during assembly of the Wendelstein 7-X divertor Endler, M.; Fellinger, J.; Hölbe, H. Plasma Physics and Controlled Fusion, Vol. 61, Issue 2 https://doi.org/10.1088/1361-6587/aaef52	journal	November 2018
On the energy confinement time in spherical tokamaks: implications for the design of pilot plants and fusion reactors Buxton, P. F.; Connor, J. W.; Costley, A. E. Plasma Physics and Controlled Fusion, Vol. 61, Issue 3 https://doi.org/10.1088/1361-6587/aaf7e5	journal	January 2019
Separating the roles of magnetic topology and neutral trapping in modifying the detachment threshold for TCV Fil, A.; Lipschultz, B.; Moulton, D. Plasma Physics and Controlled Fusion, Vol. 62, Issue 3 https://doi.org/10.1088/1361-6587/ab69bb	journal	January 2020
On similarity scaling of tokamak fusion plasmas with different aspect ratio Romanelli, Michele; Orsitto, Francesco Paolo Plasma Physics and Controlled Fusion, Vol. 63, Issue 12 https://doi.org/10.1088/1361-6587/ac2374	journal	October 2021
The role of turbulence–flow interactions in L- to H-mode transition dynamics: recent progress Schmitz, L. Nuclear Fusion, Vol. 57, Issue 2 https://doi.org/10.1088/1741-4326/57/2/025003	journal	January 2017
European DEMO design strategy and consequences for materials Federici, G.; Biel, W.; Gilbert, M. R. Nuclear Fusion, Vol. 57, Issue 9 https://doi.org/10.1088/1741-4326/57/9/092002	journal	June 2017
Heat flux mitigation by impurity seeding in high-field tokamaks Reinke, M. L. Nuclear Fusion, Vol. 57, Issue 3 https://doi.org/10.1088/1741-4326/aa5145	journal	January 2017
A gyrokinetic perspective on the JET-ILW pedestal Hatch, D. R.; Kotschenreuther, M.; Mahajan, S. Nuclear Fusion, Vol. 57, Issue 3 https://doi.org/10.1088/1741-4326/aa51e1	journal	January 2017
Overview of NSTX Upgrade initial results and modelling highlights Menard, J. E.; Allain, J. P.; Battaglia, D. J. Nuclear Fusion, Vol. 57, Issue 10, Article No. 102006 https://doi.org/10.1088/1741-4326/aa600a	journal	June 2017
Pedestal transport in H-mode plasmas for fusion gain Kotschenreuther, M.; Hatch, D. R.; Mahajan, S. Nuclear Fusion, Vol. 57, Issue 6 https://doi.org/10.1088/1741-4326/aa6416	journal	April 2017
A model of the saturation of coupled electron and ion scale gyrokinetic turbulence Staebler, G. M.; Howard, N. T.; Candy, J. Nuclear Fusion, Vol. 57, Issue 6 https://doi.org/10.1088/1741-4326/aa6bee	journal	May 2017
Self-consistent core-pedestal transport simulations with neural network accelerated models Meneghini, O.; Smith, S. P.; Snyder, P. B. Nuclear Fusion, Vol. 57, Issue 8 https://doi.org/10.1088/1741-4326/aa7776	journal	July 2017
Extension of the operational regime of the LHD towards a deuterium experiment Takeiri, Y.; Morisaki, T.; Osakabe, M. Nuclear Fusion, Vol. 57, Issue 10 https://doi.org/10.1088/1741-4326/aa7fc2	journal	August 2017
An assessment for the erosion rate of DEMO first wall Tokar, M. Z. Nuclear Fusion, Vol. 58, Issue 1 https://doi.org/10.1088/1741-4326/aa92dd	journal	November 2017
Correlation of the tokamak H-mode density limit with ballooning stability at the separatrix Eich, T.; Goldston, R. J.; Kallenbach, A. Nuclear Fusion, Vol. 58, Issue 3 https://doi.org/10.1088/1741-4326/aaa340	journal	January 2018
Scenario development during commissioning operations on the National Spherical Torus Experiment Upgrade Battaglia, D. J.; Boyer, M. D.; Gerhardt, S. Nuclear Fusion, Vol. 58, Issue 4 https://doi.org/10.1088/1741-4326/aaa6e0	journal	February 2018
Investigation of the critical edge ion heat flux for L-H transitions in Alcator C-Mod and its dependence on B _T Schmidtmayr, M.; Hughes, J. W.; Ryter, F. Nuclear Fusion, Vol. 58, Issue 5 https://doi.org/10.1088/1741-4326/aaaed0	journal	March 2018
High-resolution heat flux width measurements at reactor-level magnetic fields and observation of a unified width scaling across confinement regimes in the Alcator C-Mod tokamak Brunner, D.; LaBombard, B.; Kuang, A. Q. Nuclear Fusion, Vol. 58, Issue 9 https://doi.org/10.1088/1741-4326/aad0d6	journal	July 2018
NSTX/NSTX-U theory, modeling and analysis results Kaye, S. M.; Battaglia, D. J.; Baver, D. Nuclear Fusion, Vol. 59, Issue 11 https://doi.org/10.1088/1741-4326/ab023a	journal	June 2019
Direct gyrokinetic comparison of pedestal transport in JET with carbon and ITER-like walls Hatch, D. R.; Kotschenreuther, M.; Mahajan, S. M. Nuclear Fusion, Vol. 59, Issue 8 https://doi.org/10.1088/1741-4326/ab25bd	journal	July 2019
A simplified lithium vapor box divertor Emdee, E. D.; Goldston, R. J.; Schwartz, J. A. Nuclear Fusion, Vol. 59, Issue 8 https://doi.org/10.1088/1741-4326/ab2825	journal	July 2019
High performance double-null plasmas under radiating divertor and mantle scenarios on DIII-D Petrie, T. W.; Grierson, B. A.; Osborne, T. Nuclear Fusion, Vol. 59, Issue 8 https://doi.org/10.1088/1741-4326/ab2936	journal	July 2019
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
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
Comparison between SOLPS-4.3 and the Lengyel Model for ITER baseline neon-seeded plasmas Moulton, D.; Stangeby, P. C.; Bonnin, X. Nuclear Fusion, Vol. 61, Issue 4 https://doi.org/10.1088/1741-4326/abe4b2	journal	March 2021
Experiments on ST40 at high magnetic field Gryaznevich, Mikhail P. Nuclear Fusion https://doi.org/10.1088/1741-4326/ac26ee	journal	September 2021
Energy confinement in the spherical tokamak Globus-M2 with a toroidal magnetic field reaching 0.8 T Kurskiev, G. S.; Gusev, V. K.; Sakharov, N. V. Nuclear Fusion, Vol. 62, Issue 1 https://doi.org/10.1088/1741-4326/ac38c9	journal	December 2021
Power requirement for accessing the H-mode in ITER Martin, Y. R.; Takizuka, T.; Group, the ITPA CDBM H-mode Threshold Data Journal of Physics: Conference Series, Vol. 123 https://doi.org/10.1088/1742-6596/123/1/012033	journal	July 2008
Compact steady-state tokamak performance dependence on magnet and core physics limits Menard, J. E. Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141 https://doi.org/10.1098/rsta.2017.0440	journal	February 2019
High Confinement Mode and Edge Localized Mode Characteristics in a Near-Unity Aspect Ratio Tokamak Thome, K. E.; Bongard, M. W.; Barr, J. L. Physical Review Letters, Vol. 116, Issue 17, Article No. 175001 https://doi.org/10.1103/PhysRevLett.116.175001	journal	April 2016
Theory of current drive in plasmas Fisch, Nathaniel J. Reviews of Modern Physics, Vol. 59, Issue 1 https://doi.org/10.1103/revmodphys.59.175	journal	January 1987
Conceptual Design of High Field Central Solenoid for Fusion Nuclear Science Facility Zhai, Yuhu; Otto, Alexander; Kessels, Charles IEEE Transactions on Applied Superconductivity, Vol. 31, Issue 5 https://doi.org/10.1109/tasc.2021.3063056	journal	August 2021
MAST: Results and Upgrade Activities Morris, A. W. IEEE Transactions on Plasma Science, Vol. 40, Issue 3 https://doi.org/10.1109/tps.2011.2181540	journal	March 2012
Fusion Pilot Plant performance and the role of a Sustained High Power Density tokamak Menard, Jonathan; Grierson, Brian; Brown, Tom Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/1888274	dataset	January 2022
Transp Breslau, Joshua; Gorelenkova, Marina; Poli, Francesca Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/dc.20180627.4	software	June 2018
Plasma Equilibrium in Tokamaks de Blank, H. J. Fusion Science and Technology, Vol. 57, Issue 2T https://doi.org/10.13182/fst10-a9402	journal	February 2010
Bringing Fusion to the U.S. Grid Hawryluk, Richard J.; Lankford, Andrew; Cohen, Jared https://doi.org/10.17226/25991	book	December 2021

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Fusion Pilot Plant performance and the role of a Sustained High Power Density tokamak Menard, Jonathan; Grierson, Brian; Brown, Tom Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/1888274	dataset	January 2022
Fusion Pilot Plant performance and the role of a Sustained High Power Density tokamak Menard, Jonathan; Grierson, Brian; Brown, Tom Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States) https://doi.org/10.11578/1888274	dataset	January 2022

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