Benchmarking of spherical tokamak power plant design in PROCESS and SARAS

Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of ≈ ± 20 % . Mainly with plasma current, β components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.

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Publication Details

Journal
Fusion Engineering and Design
Published
2025-08-28
DOI
https://doi.org/10.1016/j.fusengdes.2025.115359
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
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article

Benchmarking of spherical tokamak power plant design in PROCESS and SARAS

S.P. Deshpande, Stuart I. Muldrew, Christopher Ashe, P.N. Maya
Fusion Engineering and Design
Magnetic confinement fusion research
article

Benchmarking of spherical tokamak power plant design in PROCESS and SARAS

S.P. Deshpande, Stuart I. Muldrew, Christopher Ashe, P.N. Maya
article en

Abstract

Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of ≈ ± 20 % . Mainly with plasma current, β components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.

Fusion Engineering and DesignVol. 221
Homi Bhabha National Institute (IN), Culham Centre for Fusion Energy (GB), Culham Science Centre (GB), Institute for Plasma Research (IN)
Openalex Percentile: Top 90%
Magnetic confinement fusion research
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