FRESCO, a simplified code for cost analysis of fusion power plants

Bustreo, Chiara; Casini, G.; Zollino, G.; Bolzonella, T.; Piovan, R.

doi:10.1016/j.fusengdes.2013.09.005

Cited by 11 publications

(3 citation statements)

References 16 publications

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“…The total electric power required to run the cryogenic plant P cryo can be estimated from P th , following the EU-DEMO studies [39][40][41] and the TREND systems code [22], as:…”

Section: Power Consumptionmentioning

confidence: 99%

Economically optimized design point of high-field stellarator power-plant

Prost,

Volpe

2024

Nucl. Fusion

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High Temperature Superconductors expand the design space of stellarator power-plants toward high magnetic fields B, enabling compact major radii $R$. The present paper scans the space of B, R and other design parameters, finding solutions that are promising from a physics and engineering standpoint, while minimizing the capital cost of the power-plant and the levelized cost of fusion electricity. Similarly, it identifies minimum-cost design points for next-step burning plasma stellarator experiments of fusion gain 1 < Q < 10. The study assumes advanced stellarator configurations of reduced aspect ratio, heated by Neutral Beam Injection. Plasma-facing, flowing liquid metal walls protect it from high heat and neutron fluxes. The study relies on analytical first-principle calculations, and established zero-dimensional empirical scaling laws. Power flows are illustrated by Sankey diagrams. Plasma operating contours are used to determine the reactor’s start-up path. Sensitivity analyses are conducted to identify the most critical reactor parameters within physics, engineering and costing, quantifying their influence on the economics of the power plants. Such 0D study suggests that the assumed next generation HTS, flowing liquid metal walls, and advances in compact plasma configurations could lead to an ignited stellarator power-plant of aspect ratio A ~ 4, R ≤ 4 m, B > 9 T, and normalized plasma pressure β ~ 5 % would minimize both the cost of electricity and capital cost while achieving a net electric power of about 1 GW.

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“…The total electric power required to run the cryogenic plant P cryo can be estimated from P th , following the EU-DEMO studies [39][40][41] and the TREND systems code [22], as:…”

Section: Power Consumptionmentioning

confidence: 99%

Economically optimized design point of high-field stellarator power-plant

Prost,

Volpe

2024

Nucl. Fusion

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“…A cost penalty for the complexity of components is not yet included in the model (costs of certain components may thus be underestimated). The PROCESS cost model has been benchmarked with the dedicated cost analysis code FRESCO which showed a reasonable agreement for the total costs of a tokamak test case with about 20% difference [63]. The cost estimates are obtained from the PROCESS cost model and will be given here as 'PROCESS currency units' (PCU) since the cost analysis is carried out for all devices in the same framework allowing a relative comparison between the individual devices while absolute values should be taken with care.…”

Section: Economic Comparisonmentioning

confidence: 99%

From W7-X to a HELIAS fusion power plant: motivation and options for an intermediate-step burning-plasma stellarator

Warmer

Beidler

Dinklage

et al. 2016

Plasma Phys. Control. Fusion

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As a starting point for a more in-depth discussion of a research strategy leading from Wendelstein 7-X to a HELIAS power plant, the respective steps in physics and engineering are considered from different vantage points. The first approach discusses the direct extrapolation of selected physics and engineering parameters. This is followed by an examination of advancing the understanding of stellarator optimisation. Finally, combining a dimensionless parameter approach with an empirical energy confinement time scaling, the necessary development steps are highlighted. From this analysis it is concluded that an intermediatestep burning-plasma stellarator is the most prudent approach to bridge the gap between W7-X and a HELIAS power plant. Using a systems code approach in combination with transport simulations, a range of possible conceptual designs is analysed. This range is exemplified by two bounding cases, a fast-track, cost-efficient device with low magnetic field and without a blanket and a device similar to a demonstration power plant with blanket and net electricity power production.

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“…These are the direct costs of the device that are complemented by indirect costs which are in the current model simply a flat rate of the direct costs. The PROCESS cost model has been benchmarked with the dedicated cost analysis code FRESCO which showed a reasonable agreement for the total construction costs with deviations on the order of 20% [34].…”

Section: A Cost Assessment and Direct Comparisonmentioning

confidence: 99%

System Code Analysis of HELIAS-Type Fusion Reactor and Economic Comparison With Tokamaks

Warmer

Torrisi

Beidler

et al. 2016

IEEE Trans. Plasma Sci.

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Systems codes are commonly employed for the analysis and conceptual design of fusion reactors. For the helicalaxis advanced stellarator (HELIAS) line a new set of systems code models have been developed to account for the stellaratorspecific 3D aspects. The models have recently been implemented in the systems code PROCESS and verified with respect to different test cases. After having established confidence in the stellarator models, systems studies were carried out for the 5-field period HELIAS case to define the accessible reactor design window. In the multidimensional physics and engineering parameter space sensitivity studies are carried out for the reactor regime to ascertain tradeoffs between different parameters and costs. Exemplary design points are analysed in more detail using the plasma operation contour approach which, for example, can be used to determine the optimum start-up path to ignition. Finally, with a common set of non-device-specific models, the PROCESS framework allows a direct comparison of tokamaks and stellarators. Although the 5-period HELIAS is a larger machine in terms of major radius, the required mass for both concepts is comparable leading to similar construction costs.

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FRESCO, a simplified code for cost analysis of fusion power plants

Cited by 11 publications

References 16 publications

Economically optimized design point of high-field stellarator power-plant

Economically optimized design point of high-field stellarator power-plant

From W7-X to a HELIAS fusion power plant: motivation and options for an intermediate-step burning-plasma stellarator

System Code Analysis of HELIAS-Type Fusion Reactor and Economic Comparison With Tokamaks

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