Novel free-boundary equilibrium and transport solver with theory-based models and its validation against ASDEX Upgrade current ramp scenarios

Fable, E.; Angioni, C.; Casson, F. J.; Told, D.; Ivanov, A. A.; Jenko, F.; McDermott, R. M.; Medvedev, S. Yu.; Pereverzev, G.; Ryter, F.; Treutterer, W.; Viezzer, E.

doi:10.1088/0741-3335/55/12/124028

Cited by 93 publications

(107 citation statements)

References 31 publications

Supporting

Mentioning

105

Contrasting

Unclassified

Order By: Relevance

“…ASTRA (cf. [27,28]) is a modelling code which can solve the radial transport equations for particles, energy and momentum. The transport coefficients can be put in, or evaluated via various models and therefore, it is a very versatile tool.…”

Section: Compare To a Realistic Astra Simulation Of The Eu Demo1 2015mentioning

confidence: 99%

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

et al. 2019

View full text Add to dashboard Cite

In the present work, the tolerable impurity level and composition for a reactor plasma using several sets of model assumptions are evaluated. Special care was taken to evaluate a comprehensive and consistent set of atomic data for 35 different elements, such that the impurity level for various elements may be studied as a function of their nuclear charge. The data set may not only be useful for the presented work or for system codes which design fusion reactors, but also for interpretation of bolometric measurements. Additionally, the predictions of the spectral distribution of the radiated power is of high quality such that soft X-ray broadband measurements may be interpreted.In the present work the data is used for predicting the radiated power in a reactor plasma, using a 0D, several variants of a 0.5D model and a realistic 1D ASTRA modelling of a DEMO plasma, i.e. the EU DEMO1 2015 design. The maximal or appropriate impurity content of a reactor plasma for all models can be determined, such that the predictions from a simplistic 0D model can be compared to less simplistic models and a proper reactor simulation. These comparisons suggest that with the simplistic models the impurity content may be estimated within a factor of about 1.5, independent of the realization of the reactor plasma. At the same time this study underlines the sensitivity of the reactor performance on the impurity mixture and especially of the He content of the plasma. Additionally, an extended 0.5D model is presented which is able to predict variations of the fusion yield Q and the He concentration, when both is known for a reference scenario. These predictions prove to be of high accuracy when compared to the 1D ASTRA modelling and thus, allow the net impact of an increased dilution and a simlutaneous temperature rise at constant plasma pressure to be evaluated. Furthermore, the parameter space is scanned with more than 10 5 model reactor plasmas demonstrating that the use of a low-Z impurity diminishes the possibility of an economical feasible reactor plasma. The main results of the parameter scan are made available via scaling formulae.

show abstract

Section: Compare To a Realistic Astra Simulation Of The Eu Demo1 2015mentioning

confidence: 99%

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

et al. 2019

View full text Add to dashboard Cite

show abstract

“…However, especially in plasmas with a (partially) de- [29] coupled to ASTRA [30,31] tached outer divertor significant levels of radiation peaking in the x-point region have been observed [32]. Figure 5 shows the situation with a radiation source of 150MW concentrated in the X-point.…”

Section: Radiation Heat Loadsmentioning

confidence: 99%

The DEMO wall load challenge

et al. 2017

View full text Add to dashboard Cite

show abstract

“…In this subsection, the interplay between the 0D model and the 1.5D transport code ASTRA [2,3] is explained. To improve the readability of the manuscript, the details about the 0D divertor model have been included in appendix II.…”

Section: Coupling To the 0d Divertor Modelmentioning

confidence: 99%

Impact of an integrated core/SOL description on theRandB_Toptimization of tokamak fusion reactors

Siccinio¹,

Fable²,

Angioni³

et al. 2017

Nucl. Fusion

View full text Add to dashboard Cite

An updated and improved version of the 0D divertor and scrapeoff layer (hencefort SOL) model published in [1] has been coupled with the 1.5D transport code ASTRA [2, 3]. The resulting numerical tool has been employed for various scans in the major radius R and in the toroidal magnetic field BT-for different aspect ratios A, safety factors q, allowable loop voltages V loop and H factors-in order to identify the most convenient choices for an electricity producing tokamak. Such scenario analysis has been carried out evaluating self-consistently, and simultaneously, both the core profile and transport effects, which significantly impact on the fusion power outcome, and the divertor heat loads, which represent one of the most critical issues in view of the realization of fusion power plants [4, 5]. The main result is that, when divertor limits are enforced, the curves at constant electrical power output are closed on themselves in the R − BT plane, and a maximum achievable power exists-i.e. no benefits would descend from a further increase of R and BT once the optimum has been reached. This result appears as an intrinsic physical limit for all those devices where a radiative SOL is needed to deal with the power exhaust, and where a lower limit on the power crossing the separatrix (e.g. because of the L-H transition) is present.

show abstract

Novel free-boundary equilibrium and transport solver with theory-based models and its validation against ASDEX Upgrade current ramp scenarios

Cited by 93 publications

References 31 publications

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

The DEMO wall load challenge

Impact of an integrated core/SOL description on theRandB_Toptimization of tokamak fusion reactors

Contact Info

Product

Resources

About

Novel free-boundary equilibrium and transport solver with theory-based models and its validation against ASDEX Upgrade current ramp scenarios

Cited by 93 publications

References 31 publications

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors

The DEMO wall load challenge

Impact of an integrated core/SOL description on theRandBToptimization of tokamak fusion reactors

Contact Info

Product

Resources

About

Impact of an integrated core/SOL description on theRandB_Toptimization of tokamak fusion reactors