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the WEST Team

Publications and source records attributed to the WEST Team.

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Integrated full pulse modeling for pellet injection in tokamaks: HPI2 model improvement and validation in WEST

Reliable modeling and control of core density is essential for reactor-relevant magnetic confinement fusion operation, motivating cryogenic pellet injection as a primary fueling actuator and the need for predictive pellet source models in integrated modeling. Here we present an upgrade of the physics-based pellet code HPI2 in which the plasmoid release spatial step is determined self-consistently from ablation physics, $dx_{var}=v_{\mathrm{pel}}\,t_{\mathrm{exit}}$ (optionally rescaled to trade accuracy for computational cost), removing an ad-hoc discretization parameter and improving numerical robustness across injection conditions. The upgraded model is first validated in stand-alone against a high-field-side pellet-fueled, ohmic, WEST discharge (#58656) by comparing synthetic and measured interferometry line-integrated density increments, obtaining a mean error of $\sim 10\%$. We then perform full-radius, time-dependent integrated modeling validation by coupling the new HPI2 within the High Fidelity Pulse Simulator (HFPS) workflow (JINTRAC/IMAS), combining JETTO with SANCO for the impurity/radiation evolution and TGLF-SAT2 for the turbulent transport. The coupled simulations reproduce the main density rise and relaxation after pellet injection and the associated electron-temperature transient, while taking into account the strong influence of tungsten radiation in WEST, supporting the consistency of HPI2 as a predictive pellet particle source in integrated modeling frameworks. Ultimately, this validation study supports the use of pellet modeling tools in integrated modeling studies for larger devices such as ITER.

physics.plasm-ph

Analysis of RF Sheath-Driven Tungsten Erosion at RF Antenna in the WEST Tokamak

This study applies the newly developed STRIPE (Simulated Transport of RF Impurity Production and Emission) framework to interpret tungsten (W) erosion at RF antenna structures in the WEST tokamak. STRIPE integrates SolEdge3x for edge plasma backgrounds, COMSOL for 3D RF sheath potentials, RustBCA for sputtering yields, and GITR for impurity transport and ion energy-angle distributions. In contrast to prior work by Kumar et al. 2025 Nucl. Fusion 65, 076039, which focused on framework validation for WEST ICRH discharge 57877, the present study provides a spatially resolved analysis of gross W erosion at both Q2 antenna limiters under ohmic and ICRH conditions. Using 2D SolEdge3x profiles in COMSOL, STRIPE captures rectified sheath potentials exceeding 300 V, leading to strong upper-limiter localization. Both poloidal and toroidal asymmetries are observed and attributed to RF sheath effects, with modeled erosion patterns deviating from experiment - highlighting sensitivity to sheath geometry and plasma resolution. High-charge-state oxygen ions (O6+-O8+) dominate erosion, while D+ contributes negligibly. A plasma composition of 1 percent oxygen and 98 percent deuterium is assumed. STRIPE predicts a 30-fold increase in gross W erosion from ohmic to ICRH phases, consistent with W-I 400.9 nm brightness measurements. Agreement within 5 percent (ohmic) and 30 percent (ICRH) demonstrates predictive capability and supports STRIPE's application in reactor-scale antenna design.

physics.plasm-ph