MANTA: a negative-triangularity NASEM-compliant fusion pilot plant

Author:

,Rutherford GORCID,Wilson H S,Saltzman A,Arnold D,Ball J LORCID,Benjamin SORCID,Bielajew RORCID,de Boucaud N,Calvo-Carrera M,Chandra RORCID,Choudhury H,Cummings C,Corsaro L,DaSilva N,Diab R,Devitre A RORCID,Ferry SORCID,Frank S JORCID,Hansen C JORCID,Jerkins J,Johnson J D,Lunia P,van de Lindt J,Mackie S,Maris A DORCID,Mandell N R,Miller M A,Mouratidis TORCID,Nelson A OORCID,Pharr MORCID,Peterson E EORCID,Rodriguez-Fernandez P,Segantin S,Tobin MORCID,Velberg AORCID,Wang A M,Wigram M,Witham J,Paz-Soldan CORCID,Whyte D G

Abstract

Abstract The MANTA (Modular Adjustable Negative Triangularity ARC-class) design study investigated how negative-triangularity (NT) may be leveraged in a compact, fusion pilot plant (FPP) to take a ‘power-handling first’ approach. The result is a pulsed, radiative, ELM-free tokamak that satisfies and exceeds the FPP requirements described in the 2021 National Academies of Sciences, Engineering, and Medicine (NASEM) report ‘Bringing Fusion to the U.S. Grid’ (2021 Bringing Fusion to the U.S. Grid). A self-consistent integrated modeling workflow predicts a fusion power of 450 MW and a plasma gain of 11.5 with only 23.5 MW of power to the scrape-off layer (SOL). This low P SOL together with impurity seeding and high density at the separatrix results in a peak heat flux of just 2.8 MW m−2. MANTA’s high aspect ratio provides space for a large central solenoid (CS), resulting in ∼15 minute inductive pulses. In spite of the high B fields on the CS and the other REBCO-based magnets, the electromagnetic stresses remain below structural and critical current density limits. Iterative optimization of neutron shielding and tritium breeding blanket yield tritium self-sufficiency with a breeding ratio of 1.15, a blanket power multiplication factor of 1.11, toroidal field coil lifetimes of 3100 ± 400 MW · yr, and poloidal field coil lifetimes of at least 890 ± 40 MW · yr. Following balance of plant modeling, MANTA is projected to generate 90 MW of net electricity at an electricity gain factor of 2.4 . Systems-level economic analysis estimates an overnight cost of US$3.4 billion, meeting the NASEM FPP requirement that this first-of-a-kind be less than US$5 billion. The toroidal field coil cost and replacement time are the most critical upfront and lifetime cost drivers, respectively.

Funder

National Science Foundation Graduate Research Fellowship Program

Commonwealth Fusion Systems

Mauricio and Carlota Botton Foundation fellowship

``la Caixa" Foundation fellowship

Ida M. Green fellowship

Fusion Energy Sciences

Publisher

IOP Publishing

Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Overview of results from the 2023 DIII-D negative triangularity campaign;Plasma Physics and Controlled Fusion;2024-09-10

2. Characterization of the ELM-free negative triangularity edge on DIII-D;Plasma Physics and Controlled Fusion;2024-09-05

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