ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

Sorbom, B. N.; Ball, J.; Palmer, T. R.; Mangiarotti, F. J.; Sierchio, J. M.; Bonoli, P.; Kasten, C.; Sutherland, D. A.; Barnard, H. S.; Haakonsen, C. B.; Goh, J.; Sung, C.; Whyte, D. G.

doi:10.1016/j.fusengdes.2015.07.008

Title: ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

Journal Article · Tue Jul 14 00:00:00 EDT 2015 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2015.07.008· OSTI ID:1548312

Sorbom, B. N. ^[1]; Ball, J. ^[1]; Palmer, T. R. ^[1]; Mangiarotti, F. J. ^[1]; Sierchio, J. M. ^[1]; Bonoli, P. ^[1]; Kasten, C. ^[1]; Sutherland, D. A. ^[1]; Barnard, H. S. ^[1]; Haakonsen, C. B. ^[1]; Goh, J. ^[1]; Sung, C. ^[1]; Whyte, D. G. ^[1]

Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

The affordable, robust, compact (ARC) reactor is the product of a conceptual design study focused on reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ~200–250 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This enables the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Q_p ≈ 13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ~63%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ~23 T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25 MW of lower hybrid and 13.6 MW of ion cyclotron fast wave power. The concluding efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio ≥ 1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900 K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.

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Research Organization:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); National Science Foundation (NSF)

Grant/Contract Number:: FG02-94ER54235; SC008435; FC02-93ER54186

OSTI ID:: 1548312

Alternate ID(s):: OSTI ID: 1252044

Journal Information:: Fusion Engineering and Design, Vol. 100, Issue C; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 280 works

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Spatiotemporal evolution of runaway electrons from synchrotron images in Alcator C-Mod Tinguely, R. A.; Granetz, R. S.; Hoppe, M. arXiv https://doi.org/10.48550/arxiv.1810.02742	text	January 2018
The effect of background flow shear on gyrokinetic turbulence in the cold ion limit Ball, Justin; Brunner, Stephan; McMillan, Ben F. arXiv https://doi.org/10.48550/arxiv.1812.08566	text	January 2018
Maximizing specific energy by breeding deuterium Ball, Justin arXiv https://doi.org/10.48550/arxiv.1908.00834	text	January 2019
ARC reactor materials: Activation analysis and optimization Bocci, B.; Hartwig, Z.; Segantin, S. Fusion Engineering and Design, Vol. 154 https://doi.org/10.1016/j.fusengdes.2020.111539	journal	May 2020
Upward shift of the vortex solid phase in high-temperature-superconducting wires through high density nanoparticle addition Miura, Masashi; Maiorov, Boris; Balakirev, Fedor F. Scientific Reports, Vol. 6, Issue 1 https://doi.org/10.1038/srep20436	journal	February 2016
Alpha channeling with high-field launch of lower hybrid waves Ochs, I. E.; Bertelli, N.; Fisch, N. J. Physics of Plasmas, Vol. 22, Issue 11 https://doi.org/10.1063/1.4935123	journal	November 2015
Measurements of the Strain Dependence of Critical Current of Commercial REBCO Tapes at 15 T Between 4.2 and 40 K for High Field Magnets Pierro, Federica; Delgado, Mario; Chiesa, Luisa IEEE Transactions on Applied Superconductivity, Vol. 29, Issue 5 https://doi.org/10.1109/tasc.2019.2902458	journal	August 2019
Neutron diagnostics for the physics of a high-field, compact, $Q\geq1$ tokamak Tinguely, R. A.; Rosenthal, A.; Simpson, R. arXiv https://doi.org/10.48550/arxiv.1903.09479	preprint	January 2019
A high temperature W$_2$B cermet for compact neutron shielding Athanasakis, Michail; Ivanov, Eugene; del Rio, Eduardo arXiv https://doi.org/10.48550/arxiv.1912.04671	text	January 2019

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