TRANSP integrated modeling code for interpretive and predictive analysis of tokamak plasmas

Pankin, A. Y.; Breslau, J.; Gorelenkova, M.; Andre, R.; Grierson, B.; Sachdev, J.; Goliyad, M.; Perumpilly, G.

doi:10.1016/j.cpc.2025.109611

TRANSP integrated modeling code for interpretive and predictive analysis of tokamak plasmas

Journal Article · Wed Apr 09 00:00:00 EDT 2025 · Computer Physics Communications

DOI:https://doi.org/10.1016/j.cpc.2025.109611· OSTI ID:2551910

^[1]; Breslau, J. ^[1]; Gorelenkova, M. ^[1]; Andre, R. ^[1]; Grierson, B. ^[2]; Sachdev, J. ^[1]; Goliyad, M. ^[1]; Perumpilly, G. ^[1]

Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
General Atomics, San Diego, CA (United States)

This paper provides a comprehensive review of the TRANSP code, a sophisticated tool for interpretive and predictive analysis of tokamak plasmas, detailing its major capabilities and features. It describes the equations for particle, power, and momentum balance analysis, as well as the poloidal field diffusion equations. The paper outlines the spatial and time grids used in TRANSP and details the equilibrium assumptions and solvers. Various models for heating and current drive and radiation, including updates to the NUBEAM model, are discussed. The handling of large-scale events such as sawtooth crashes and pellet injections is examined, along with the predictive capabilities for advancing plasma profiles. The integration of TRANSP with the ITER Integrated Modeling and Analysis Suite (IMAS) is highlighted, demonstrating enhanced data access and analysis capabilities. Additionally, the paper discusses best practices and continuous integration techniques to enhance TRANSP's robustness. The suite of TRANSP tools, designed for efficient data analysis and simulation, further supports the optimization of tokamak operations and coupling with other tokamak codes. Continuous development and support ensure that TRANSP remains a major code for the analysis of experimental data for controlled thermonuclear fusion, maintaining its critical role in supporting the optimization of tokamak operations and advancing fusion research.

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Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

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

Grant/Contract Number:: AC02-05CH11231; AC02-09CH11466

OSTI ID:: 2551910

Alternate ID(s):: OSTI ID: 2564368

Journal Information:: Computer Physics Communications, Journal Name: Computer Physics Communications Vol. 312; ISSN 0010-4655

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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TRANSP integrated modeling code for interpretive and predictive analysis of tokamak plasmas

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