E. Tholerus

Self-consistent modeling of STEP flat top scenario with realistic electron cyclotron heating and current drive

R. Sharma, S. J. Freethy, D. Brunetti, F. J. Casson et autres

Abstract The spherical tokamak for energy production (STEP) is the UK’s flagship program to design a prototype fusion power plant capable of delivering net electricity to the grid. Due to geometric constraints in spherical tokamaks, STEP is being developed for fully non-inductive …

gb, it (code pays fourni par la source)

Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors

B. Kool, K. Verhaegh, Gijs Derks, J.T.W. Koenders et autres

Abstract Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge. This is compounded in emerging compact reactor designs promising more cost-effective pathways towards commercial fusion energy. …

nl, gb, us, de, ch, it, cz, at, fi, be, gr, se, fr, hu, es, pl, pt (code pays fourni par la source)

Fusion alpha power control optimisation using RAPTOR

J. Mitchell, Arka Mitra, S. Van Mulders, F. J. Casson et autres

The Spherical Tokamak for Energy Production (STEP) is a prototype fusion power plant planned to be operational in the 2040s. STEP’s interaction with the national grid and its responsiveness to demand hinges largely on the effective control of the energy released during …

gb, ch (code pays fourni par la source)

ITPA TC-33 benchmark: ITER Ip=15 MA reference case

C. Bourdelle, F. Koechl, E. Tholerus, M. Schneider et autres

This record contains an ITER Ip=15 MA benchmark case in IMAS format, coming from ITPA TC-33 joint activity It is composed of two datasets that correspond to t=415 s (obtained after 95 s of current diffusion) and t=450 s (obtained after 30 …

fr, gb, se (code pays fourni par la source)

ITPA TC-33 benchmark: ITER Ip=15 MA reference case

C. Bourdelle, F. Koechl, E. Tholerus, M. Schneider et autres

This record contains an ITER Ip=15 MA benchmark case in IMAS format, coming from ITPA TC-33 joint activity It is composed of two datasets that correspond to t=415 s (obtained after 95 s of current diffusion) and t=450 s (obtained after 30 …

fr, gb, se (code pays fourni par la source)

Heating and current drive in STEP: why neutral beam injection is not desirable

T. Wilson, Hana El-Haroun, Anurag Saigiridhari, E. Tholerus

Abstract Spherical Tokamak for Energy Production (STEP) is the UK’s prototype fusion power plant programme aiming to demonstrate net electrical output from a spherical tokamak. The plasma scenarios require a completely non-inductive current drive for the flat-top and the majority of the …

gb (code pays fourni par la source)

Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC

E. Tholerus, L. Garzotti, V. Parail, Yuriy Baranov et autres

Abstract In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons …

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Non-linear dependence of ion heat flux on plasma density at the L–H transition of JET NBI-heated deuterium–tritium plasmas

P. Vincenzi, E.R. Solano, E. Delabie, C. Angioni et autres

Abstract Recent JET D–T campaigns opened the possibility of unique isotope studies to investigate the L–H transition physics in view of reactor plasmas and to study the origin of the observed power threshold minimum. In the present paper, we characterise L–H transitions …

it, us, de, gb (code pays fourni par la source)

Simulations of the stationary Q = 10 and the exit phase from the flat-top of an ITER 15MA baseline scenario: predictive JINTRAC simulation with a consistent treatment of D and T in the whole plasma

F. Eriksson, E. Tholerus, Gerard Corrigan, Yuriy Baranov et autres

Abstract Designing a robust termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, to study the Q = 10 flat-top …

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Flat-top plasma operational space of the STEP power plant

E. Tholerus, F. J. Casson, S. P. Marsden, D. Brunetti et autres

Abstract STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, …

Access and sustainment of ELMy H-mode operation for ITER Pre-Fusion Power Operation plasmas using JINTRAC

E. Tholerus, L. Garzotti, V. V. Parail, Y. Baranov et autres

In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons from …

gb, fr, it, se (code pays fourni par la source)

A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors

A. Murari, Riccardo Rossi, T. Craciunescu, J. Vega et autres

The objective of thermonuclear fusion consists of producing electricity from the coalescence of light nuclei in high temperature plasmas. The most promising route to fusion envisages the confinement of such plasmas with magnetic fields, whose most studied configuration is the tokamak. Disruptions …

it, ro, es, gb, pt, pl, ru, fi, jp, gr, fr, se, de, us, hu, lv, ch (code pays fourni par la source)