1 Introduction
The knowledge of plasma composition impacts the estimation of many relevant quantities in magnetic-controlled fusion plasmas. Minority species, both hydrogenic and impurity, can strongly affect the absorption of ion-cyclotron resonance frequency (ICRF) heating, the deposition profile of neutral beam injection (NBI), the shape of the current density profile as well as the fusion rate. Over the decades, various spectroscopic diagnostics and analysis methodologies have been developed to estimate the impurity densities and plasma effective charge (see e.g. Behringer et al. (Reference Behringer, Carolan, Denne, Decker, Engelhardt, Forrest, Gill, Gottardi, Hawkes and Källne1986), Rathgeber et al. (Reference Rathgeber, Fischer, Fietz, Hobirk, Kallenbach, Meister, Pütterich, Ryter, Tardini and Wolfrum2010), Czarnecka et al. (Reference Czarnecka, Zastrow, Rzadkiewicz, Coffey, Lawson and O’Mullane2011), Pütterich et al. (Reference Pütterich, Dux, Beurskens, Bobkov, Brezinsek, Bucalossi, Coenen, Coffey, Czarnecka and Giroud2012), Reinke et al. (Reference Reinke, Hutchinson, Rice, Howard, Bader, Wukitch, Lin, Pace, Hubbard and Hughes2012), Coenen et al. (Reference Coenen, Sertoli, Brezinsek, Coffey, Dux, Giroud, Groth, Huber, Ivanova and Krieger2013), McDermott et al. (Reference McDermott, Dux, Pütterich, Geiger, Kappatou, Lebschy, Bruhn, Cavedon, Frank and den Harder2018), Odstrcil et al. (Reference Odstrcil, Pütterich, Angioni, Bilato, Gude, Odstrcil and Team2018), Sertoli et al. (Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018) and reference therein) and on these results depend the conclusions drawn by complex analysis and modelling of present experiments as well as predictions for future machines such as ITER or DEMO (see e.g. Dux & Peeters (Reference Dux and Peeters2000), Kallenbach et al. (Reference Kallenbach, Neu, Dux, Fahrbach, Fuchs, Giannone, Gruber, Herrmann, Lang and Lipschultz2005), Pacher et al. (Reference Pacher, Pacher, Janeschitz, Kukushkin, Kotov and Reiter2007), Delgado-Aparicio et al. (Reference Delgado-Aparicio, Stutman, Tritz, Volpe, Wong, Bell, Finkenthal, Fredrickson, Gerhardt and Kaye2011), Lerche et al. (Reference Lerche, Eester, Ongena, Mayoral, Laxaback, Rimini, Argouarch, Beaumont, Blackman and Bobkov2011), Tardini et al. (Reference Tardini, Fischer, Jenko, Kallenbach, McDermott, Pütterich, Rathgeber, Schneller, Schweinzer and Sips2012), Beurskens et al. (Reference Beurskens, Schweinzer, Angioni, Burckhart, Challis, Chapman, Fischer, Flanagan, Frassinetti and Giroud2013), Kallenbach et al. (Reference Kallenbach, Bernert, Dux, Casali, Eich, Giannone, Herrmann, McDermott, Mlynek and Müller2013), Zagórski, Ivanova-Stanik & Stankiewicz (Reference Zagórski, Ivanova-Stanik and Stankiewicz2013), Loarte et al. (Reference Loarte, Reinke, Polevoi, Hosokawa, Chilenski, Howard, Hubbard, Hughes, Rice and Walk2015) and Breton et al. (Reference Breton, Casson, Bourdelle, Citrin, Baranov, Camenen, Challis, Corrigan, Garcia and Garzotti2018a )). These diagnostics and analysis methodologies each typically give information on one impurity element at a time, usually of one single ionization stage. They are often line-of-sight (LoS) integrals over one single chord and are in general analysed independently. In tokamaks such as ITER and JET with the ITER-like wall (ILW) with multi-elemental plasma-facing components (PFCs) including low- (Be), mid- (Ni, Fe, Cr, Cu) and high-Z materials (Mo, W), as well seeding gases (e.g. N, Ne), the problem of providing a clear and coherent picture of the plasma composition is thus an arduous, but critical task. This can lead to a better understanding of the physics and the gaining of confidence in or falsifying of the available models, as well as giving more precise indications on the impurities responsible for performance degradation or disruptions. In all the above cases, a correct identification of the impurity species can provide vital information to improve its control, while inappropriately holding one element responsible may lead to erroneous and futile actions.
The method described in this contribution aims at providing a coherent, integrated picture of the plasma composition by combining as much information as possible from various diagnostics. For the case of JET-ILW these include (figure 1):
(i) soft X-ray (SXR) radiation: SXR-diode array camera V (Sertoli et al. Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018), vertical view, 35 LoS, $250~\unicode[STIX]{x03BC}\text{m}$ Be-filter, integrated radiated power in photon energy range $1.5<E_{\unicode[STIX]{x1D6FE}}<10~(\text{keV})$ .
(ii) Total radiation: foil bolometer arrays (Huber et al. Reference Huber, McCormick, Andrew, Beaumont, Dalley, Fink, Fuchs, Fullard, Fundamenski and Ingesson2007), cameras V and H, 14 vertical and horizontal LoS not viewing the divertor.
(iii) W concentration: grazing-incidence vacuum-ultra-violet (VUV) spectrometer viewing in a small wavelength range close to 5 nm along one vertical LoS (Schwob et al. Reference Schwob, Wouters, Suckewer and Finkenthal1987) providing two independent measurements localized close to $T_{e}\sim 1.5~\text{keV}$ and $T_{e}\sim 3.5~\text{keV}$ (Pütterich et al. Reference Pütterich, Neu, Dux, Whiteford and O’Mullane2008).
(iv) Effective charge $Z_{\text{eff}}$ : spectroscopy of visible bremsstrahlung along one horizontal and one vertical LoS (Behringer et al. Reference Behringer, Carolan, Denne, Decker, Engelhardt, Forrest, Gill, Gottardi, Hawkes and Källne1986).
(v) Toroidal rotation and ion temperature: charge-exchange-recombination spectroscopy (CXRS) measurements at ${\sim}10$ radial positions close to the low field side (LFS) mid-plane (Menmuir et al. Reference Menmuir, Giroud, Biewer, Coffey, Delabie, Hawkes and Sertoli2014).
(vi) Electron temperature and density: Thomson scattering (HRTS) measurements at ${\sim}60$ radial positions close to the LFS mid-plane (Pasqualotto et al. Reference Pasqualotto, Nielsen, Gowers, Beurskens, Kempenaars, Carlstrom and Johnson2004; Frassinetti et al. Reference Frassinetti, Beurskens, Scannell, Osborne, Flanagan, Kempenaars, Maslov, Pasqualotto and Walsh2012).
Additional information can also be included for the following quantities: electron density and temperature measurements from light detection and ranging (LIDAR) Thomson scattering (Maslov et al. Reference Maslov, Beurskens, Kempenaars and Flanagan2013) or electron-cyclotron emission diagnostics (de la Luna et al. Reference de la Luna, Sánchez, Tribaldos, Conway, Suttrop, Fessey, Prentice, Gowers and Chareau2004); Zeff measurement along the vertical LoS of visible spectroscopy measurements; Ni concentration measurement from the X-ray crystal spectrometer measuring He-like Ni (Shumack et al. Reference Shumack, Rzadkiewicz, Chernyshova, Jakubowska, Scholz, Byszuk, Cieszewski, Czarski, Dominik and Karpinski2014); information on the impurity content from other UV spectrometers; toroidal rotation estimate of the X-ray crystal spectrometer or magneto-hydro-dynamic (MHD) markers. All of these diagnostics are analysed on the same equilibrium fitting (EFIT) equilibrium reconstruction (Lao et al. Reference Lao, John, Stambaugh, Kellman and Pfeiffer1985) performed using only magnetic measurements, accounting for possible corrections identically for all measurement positions and LoS.
An overview of the whole method will be given in § 2, concentrating mainly on the most recent extensions to account for multiple low-Z and medium-/high-Z elements. In § 3 a case discharge will be analysed, describing in depth the stepwise inclusion of multiple impurities searching for the best match to all the available diagnostic measurements. Discussion on the result, conclusions and an outlook are given in § 4.
2 Experimental method
The extension of the method starts with a generalization of equation (4) from Sertoli et al. (Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018) for any impurity species (not just tungsten) of atomic number $Z_{0}$ dominating the SXR diagnostic brightness and the inclusion of additional secondary impurities $s$ ,
where $M$ is a constant, $\unicode[STIX]{x1D716}_{exp}^{SXR}$ the experimental SXR emissivity, $n$ the density of electrons ( $e$ ), main ion ( $I$ , i.e. either H, D, or T) and impurities ( $s$ ), $L^{SXR}$ the SXR-filtered cooling function, i.e. the radiation loss parameter per unit electron and ion densities (in units of $\text{W}~\text{m}^{3}$ ) filtered in the energy range detected by the diagnostic. Identically to previous studies, the application of (2.1) is limited radially by the view of the SXR camera V used in the analysis and by the cutoff in the SXR filter function $Te>1.5~\text{keV}$ . The ionization balance and cooling functions (total and SXR-filtered) are all modelled in local ionization equilibrium (LIE), i.e. neglecting the effect of transport. As already shown in previous publications, this is a valid assumption for the core plasma, especially for mid-/high-Z impurities, but may be violated in the pedestal region due to large gradients and fast transport time scales in comparison to the ionization and recombination rates. The atomic data used in this work come from Pütterich et al. (Reference Pütterich, Dux, Beurskens, Bobkov, Brezinsek, Bucalossi, Coenen, Coffey, Czarnecka and Giroud2012) and Casson et al. (Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015) for the SXR cooling functions and the ionization/recombination, from Pütterich et al. (Reference Pütterich, Fable, Dux, O’Mullane, Neu and Siccinio2019) for the total radiated power.
While the solution of this equation neglecting secondary impurities is straightforward, including even just one increases dramatically the number of free parameters. First of all, each impurity typically has its own source term which depends on its origin (main chamber PFCs, ion-cyclotron-resonance-heating (ICRH) antenna limiters, NBI duct scraper, divertor tiles, gas valves, etc.) and can be independently influenced by other actuators (gas puffing, edge-localized-mode (ELM) frequency, heating power, etc.). Moreover, their radial transport depends strongly on mass and charge, especially in JET high power discharges where the central impurity transport is mostly neoclassical (Angioni et al. Reference Angioni, Mantica, Pütterich, Valisa, Baruzzo, Belli, Belo, Casson, Challis and Drewelow2014, Reference Angioni, Casson, Mantica, Pütterich, Valisa, Belli, Bilato, Giroud and Helander2015; Casson et al. Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015). Finally, heavy elements are often asymmetric on the flux surfaces, driven mainly by centrifugal forces (Ingesson et al. Reference Ingesson, Alper, Chen, Edwards, Fehmers, Fuchs, Giannella, Gill, Lauro-Taroni and Romanelli1998; Reinke et al. Reference Reinke, Hutchinson, Rice, Howard, Bader, Wukitch, Lin, Pace, Hubbard and Hughes2012; Casson et al. Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015; Odstrcil et al. Reference Odstrcil, Pütterich, Angioni, Bilato, Gude, Odstrcil and Team2018), while lighter elements are not. Solving (2.1) with secondary impurities therefore requires a certain number of assumptions driven by the present theoretical understanding of impurity transport.
2.1 Inclusion of multiple low-Z impurities
As in the original method (Sertoli et al. Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018), light elements are included in the analysis assuming that their concentration profile is flat and symmetric on the flux surface $n_{Z_{1}}(\unicode[STIX]{x1D70C};t)=c_{Z_{1}}(t)\cdot n_{e}(\unicode[STIX]{x1D70C};t)$ . Due to their low mass and in ion temperature gradient (ITG) turbulence regimes such as those usually encountered at JET, these assumptions are supported by the current theoretical understanding (Angioni et al. Reference Angioni, McDermott, Fable, Fischer, Pütterich, Ryter and Tardini2011; Bonanomi et al. Reference Bonanomi, Mantica, Giroud, Angioni, Manas and Menmuir2018; Bourdelle et al. Reference Bourdelle, Camenen, Citrin, Marin, Casson, Koechl and Maslov2018; McDermott et al. Reference McDermott, Dux, Pütterich, Geiger, Kappatou, Lebschy, Bruhn, Cavedon, Frank and den Harder2018; Kappatou et al. Reference Kappatou, McDermott, Angioni, Manas, Pütterich, Dux, Viezzer, Jaspers, Fischer and Dunne2019).
The concentration is free to evolve in time and is calculated from the visible Bremsstrahlung LoS-averaged $Z_{\text{eff}}$ measurement (Behringer et al. Reference Behringer, Carolan, Denne, Decker, Engelhardt, Forrest, Gill, Gottardi, Hawkes and Källne1986) accounting for contributions of all the other impurities to the LoS integral,
$n_{s}$ and $n_{e}$ are the impurity and electron densities respectively, $\langle q_{s}\rangle$ the impurity average charge (in units of the elementary charge), $L$ the LoS length and the sum is performed over all impurities excluding $Z_{1}$ . Differently from Sertoli et al. (Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018), the contribution from each impurity is thus modelled self-consistently along the LoS accounting for poloidal asymmetries of the mid-/high-Z impurity densities $n_{s}(\unicode[STIX]{x1D70C},R;t)$ . In this and later equations, quantities assumed symmetric on the flux surface (impurity average charge, electron temperature and density, factors, etc.) will have a radial dependence $(\unicode[STIX]{x1D70C})$ , while those which may exhibit poloidal asymmetries are estimated in two dimensions on the $(R,z)$ plane and will have a radial dependence $(\unicode[STIX]{x1D70C},R)$ . The flux-surface label $\unicode[STIX]{x1D70C}$ is retained instead of $z$ in order not to lose the information on the parent flux surface. The flux-surface label $\unicode[STIX]{x1D70C}$ used in from now on corresponds to the normalized poloidal flux coordinate $\unicode[STIX]{x1D70C}_{pol}=\sqrt{(\unicode[STIX]{x1D713}-\unicode[STIX]{x1D713}_{a})/(\unicode[STIX]{x1D713}_{s}-\unicode[STIX]{x1D713}_{a})}$ , where indices $s$ and $a$ refer to the separatrix and the magnetic axis respectively.
A secondary low-Z impurity $Z_{2}$ can be added with the additional constraint that the concentration is constant in time $n_{Z_{2}}(\unicode[STIX]{x1D70C},t)=c_{Z_{2}}\cdot n_{e}(\unicode[STIX]{x1D70C},t)$ . For the case of JET-ILW discharges without impurity seeding, Be is used as primary low-Z ( $Z_{1}$ ). If instead seeding takes place, Be is set as the constant background ( $Z_{2}$ ) and the seeding gas is set as primary and left free to evolve in time. The constant Be concentration is calculated from the $Z_{\text{eff}}$ measurement prior to the seeding phase assuming it is the only other low-Z impurity. Typical concentrations are of the order of 0.5 %–2.0 %.
After having applied (2.1) with the chosen low-Z impurities, if the main impurity $Z_{0}$ is tungsten the first guess of the impurity density is re-scaled comparing the result with the independent measurement from VUV spectroscopy (Schwob et al. Reference Schwob, Wouters, Suckewer and Finkenthal1987; Pütterich et al. Reference Pütterich, Neu, Dux, Whiteford and O’Mullane2008),
where $c_{W}$ is the VUV spectrometer measurement and $c_{W}^{SXR}$ the simulated one integrating $n_{W}^{SXR}$ from (2.1) along the LoS of the VUV spectrometer and weighing it on the fractional abundance envelope of the measured ionization stages. This provides a first consistency check of the absolute W density with the assumption that it is the major contributor to the SXR emissivity, but accounting for the fact that contributions from other impurities might be present. For further details, see § II A of Sertoli et al. (Reference Sertoli, Angioni and Odstrcil2017) and references therein.
This density is then used to evaluate a re-calibration factor for the SXR emissivity,
where $\unicode[STIX]{x1D716}_{exp}^{SXR}$ is the result of the deconvolution routine and the average is performed over the whole time range of interest and over the plasma radius within the range of validity of the analysis, and contributions of all other secondary impurities $s$ are accounted for. The process is iterated a few times until convergence (two iterations have been found to suffice) after which the re-scaling versus the W concentration measurement is abandoned and the SXR multiplication factor is the only correction that is retained. If the main impurity is not W, then this multiplication factor is set to $M=3$ , a value previously estimated by comparing the SXR emissivity with bolometry in plasmas with a dominant low-Z impurity and negligible contributions from mid-/high-Z elements (Pütterich et al. Reference Pütterich, Dux, Beurskens, Bobkov, Brezinsek, Bucalossi, Coenen, Coffey, Czarnecka and Giroud2012). As a confirmation of this previous estimate, multiplication factors of the order of $2.5{-}3.5$ have been found for all those cases that show good consistency with other diagnostic measurements, where the main impurity is W and the W concentration measurements from VUV was available. This re-calibration factor $M$ is JET-specific and its origin is still not understood. It could be tied to uncertainties in the Be-filter thickness, in the atomic data or in the diagnostic acquisition, but the fact that it is constant over time and independent of plasma scenario legitimizes treating it as a re-calibration factor.
After having calculated the multiplication factor, equation (2.1) is re-applied and the whole procedure repeated until convergence (two more times are typically enough). Consistency checks with independent measurements are then applied to falsify or confirm the results obtained so far.
2.2 Consistency checks versus independent measurements
On top of the consistency checks already used in the original method (Sertoli et al. Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018) which are listed below as (i–iii), a few more have been implemented to provide further robustness to the methodology:
(i) if the main impurity $Z_{0}$ is tungsten, compare its time evolution with the independent concentration measurement from VUV spectroscopy;
(ii) from the observed LFS-high-field-side (HFS) asymmetry of $Z_{0}$ evaluate the expected toroidal rotation and compare with CXRS measurements;
(iii) including contributions from all ions, calculate the total radiation (in two dimensions) and compare with estimates tomographic reconstructions of the bolometry diagnostic;
(iv) integrate the estimated total radiation along the LoS of the bolometry diagnostic and compare with the experimental values;
(v) if a seeding gas is included, compare the time evolution and absolute value of the independent concentration measurement from CXRS.
While checks (i)–(iii) and (v) are relatively straightforward, comparing with LoS integrals of bolometry requires an extrapolation of the results beyond the range of validity of the analysis. This is a delicate part and will be explained in the next section.
2.3 Inclusion of a secondary mid-/high-Z impurities
If the solution of (2.1) including only low-Z impurities yields estimates that do not match the consistency checks within the estimated experimental uncertainties, one more impurity $Z_{3}$ can be added to the mix. This can be a mid-/high-Z element and its time evolution, profile shape and asymmetry are modelled on the basis of $n_{Z_{0}}$ with the following assumptions:
(i) both impurities $Z_{0}$ and $Z_{3}$ are at equilibrium, the impurity sources and sinks do not change during the time range of analysis and the time averaging is long enough (typically 20 ms) such that the net particle flux through the separatrix is zero. If this is not the case, the sources and sinks of both impurities are assumed to behave identically;
(ii) the central peaking of $Z_{0}$ and $Z_{3}$ is driven by neoclassical processes;
(iii) poloidal asymmetries are driven mainly by centrifugal effects.
If the peaking of the impurity density profiles in the plasma centre is neoclassically driven, as it typically is in the centre of JET H-mode plasmas (Angioni et al. Reference Angioni, Casson, Mantica, Pütterich, Valisa, Belli, Bilato, Giroud and Helander2015; Casson et al. Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015), the radial impurity flux can be modelled following Breton et al. (Reference Breton, Casson, Bourdelle, Angioni, Belli, Camenen, Citrin, Garbet, Sarazin and Sertoli2018b , equation (7)). If the particle flux is zero and the profiles are in equilibrium, the normalized impurity density gradient can then be calculated as,
where $R$ is the tokamak major radius, $L_{A}=A/\unicode[STIX]{x1D735}A$ the gradient length of quantity $A$ , $m_{I}$ the mass of the main ion $I$ and $T_{I}$ its temperature, $q_{s}$ the impurity charge, $H$ , $H_{0}$ and $K$ factors that depend on the collisionality, $f_{c}$ the fraction of circulating particles, $P_{A}$ and $P_{B}$ the geometrical factors related to poloidal asymmetries (Casson et al. Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015; Breton et al. Reference Breton, Casson, Bourdelle, Angioni, Belli, Camenen, Citrin, Garbet, Sarazin and Sertoli2018b ). All quantities are flux-surface averages (FSA), including the left-hand side of the equation. The subscript $FSA$ will be neglected from now on, but the symbol $\langle \,\rangle$ will retain the meaning of flux-surface-averaged quantity.
For peaked profiles, the pinch term proportional to $R/L_{n_{I}}$ will dominate over both the ion temperature screening term proportional to $R/L_{T_{I}}$ as well as turbulence. Neglecting at first order the temperature screening term, the normalized impurity density gradient becomes directly proportional to the main ion gradient multiplied by the impurity charge $q_{s}$ . Using the previously estimated density profile of impurity $Z_{0}$ , the gradients of the secondary impurity $Z_{3}$ can be calculated as,
Inverting this equation will then yield the shape of the impurity density profile,
Since this re-adaptation of the flux-surface-averaged impurity density gradient is not performed in absolute terms with respect to $R/L_{n_{I}}$ , but relative to the primary impurity $Z_{0}$ whose gradient is determined experimentally, second-order effects mitigating the impurity peaking coming from neoclassical temperature screening and turbulence are still somewhat retained.
In regions of the plasma where the profile of impurity $Z_{0}$ is flat or hollow, then neoclassical temperature screening or turbulence will dominate over the neoclassical pinch term. In JET-ILW plasmas the former is usually responsible for effects close to the plasma centre, while the latter is typically the dominating transport mechanism for radii $\unicode[STIX]{x1D70C}>0.3{-}0.4$ and will lead to profiles $n_{s}\propto n_{e}$ (Angioni et al. Reference Angioni, Casson, Mantica, Pütterich, Valisa, Belli, Bilato, Giroud and Helander2015; Casson et al. Reference Casson, Angioni, Belli, Bilato, Mantica, Odstrcil, Pütterich, Valisa, Garzotti and Giroud2015; Bourdelle et al. Reference Bourdelle, Camenen, Citrin, Marin, Casson, Koechl and Maslov2018). In this case, the flux-surface-averaged impurity density gradient of $Z_{3}$ will be set equal to that of the primary high-Z impurity $L_{n_{Z_{3}}}=L_{n_{Z_{0}}}$ .
For the determination of the absolute value and time evolution, assumption $(i)$ provides the necessary framework by imposing that the flux-surface-averaged density profile of $Z_{3}$ follows closely that of $Z_{0}$ . The result of (2.7) is thus normalized by setting the total number of $Z_{3}$ ions in the confined region equal to that of $Z_{0}$ at each time point,
and finally multiplying by a constant $C$ which is a single number for the whole time range of analysis
This constant has the meaning of the fraction of the total impurity density of $Z_{3}$ with respect to $Z_{0}$ . This is evaluated applying consistency check (d) comparing the LoS integrals of the bolometric diagnostic with its synthetic value estimated from the two-dimensional (2-D) maps of the total radiation calculated including contributions from the main ion and all impurities,
where the sum is performed over $N$ lines of sight of length $L_{k}$ and $B_{k}^{\text{bolo}}$ are the experimental LoS-integrals. Since the method for the equation can be applied above $T_{e}(\unicode[STIX]{x1D70C}_{\max })=1.5~\text{keV}$ , the densities $n_{Z_{0}}$ and $n_{Z_{3}}$ must be extrapolated from $\unicode[STIX]{x1D70C}_{\max }$ up to the separatrix. This can be done in a number of ways, including scaling the electron density over the whole region $\unicode[STIX]{x1D70C}>\unicode[STIX]{x1D70C}_{\max }$ or extrapolating the value or the derivative up to a specified radius $\unicode[STIX]{x1D70C}_{\text{interp}}$ and then following the shape of the electron density scaled to match the impurity density at $\unicode[STIX]{x1D70C}_{\text{interp}}$ . All of these methods are performed on the mid-plane values of the 2-D impurity densities, independently for LFS and HFS, to maintain the observed asymmetry at $\unicode[STIX]{x1D70C}_{\max }$ . For the pedestal region, in order to artificially compensate for the underestimated cooling functions calculated neglecting transport, the impurity density is slightly enhanced by increasing the pedestal value to $n_{Z_{0}}(\unicode[STIX]{x1D70C}>0.9)=(n_{Z_{0},n_{e}}+n_{Z_{0}}(\unicode[STIX]{x1D70C}>0.9))/2$ .
The last point to clarify is how to evaluate the poloidal asymmetry of $Z_{3}$ . This is straightforward if assumption (iii) is valid and an estimate of the toroidal rotation profile is available. Following equation (9) of Odstrcil et al. (Reference Odstrcil, Pütterich, Angioni, Bilato, Gude, Odstrcil and Team2018) and neglecting the asymmetries driven by fast particles (first term on the right-hand side), the impurity density on a flux surface $\unicode[STIX]{x1D70C}$ at a generic mayor radius $R$ can be calculated with respect to the value at a reference major radius $R_{0}$ ,
where the asymmetry parameter $\unicode[STIX]{x1D706}_{s}$ is fully determined by knowing the main ion and impurity masses ( $m_{I}$ and $m_{s}$ ), the average impurity charge $\langle q_{s}\rangle$ , the effective charge $Z_{\text{eff}}$ , the electron and ion temperatures $T_{e,I}$ and the toroidal rotation frequency $\unicode[STIX]{x1D714}_{\unicode[STIX]{x1D719}}$ ,
The impurity density at the chosen reference radius $R_{0}$ on the LFS mid-plane can then be estimated by inverting (2.11) and calculating the flux-surface-averaged value of the exponent,
All other quantities in (2.12) are already included in the analysis or self-consistently calculated using the available profile data.
The toroidal rotation and ion temperature are taken from CXRS measurements on impurity ions (e.g. $Ne\,X$ ) and are assumed equal for all impurities. This assumption is consistent with previous findings (Baylor et al. Reference Baylor, Burrell, Groebner, Houlberg, Ernst, Murakami and Wade2004; Lebschy Reference Lebschy2018; Grierson et al. Reference Grierson, Chrystal, Haskey, Wang, Rhodes, McKee, Barada, Yuan, Nave and Ashourvan2019) and can be confirmed here for consistency using the radial force balance equation $E_{r}=\unicode[STIX]{x1D735}p/qn+v_{\unicode[STIX]{x1D719}}B_{\unicode[STIX]{x1D717}}-v_{\unicode[STIX]{x1D717}}B_{\unicode[STIX]{x1D719}}$ . Since the radial electric field will be equal for all species, with the assumption that their temperatures are the same, that their peaking follows (2.6) and that the poloidal flow term is negligible at first order, the difference between the toroidal velocities of two ions will be,
with $\unicode[STIX]{x1D735}T$ given in $(\text{eV}/\text{m})$ and $B_{\unicode[STIX]{x1D717}}(T)$ . This leads to small differences for impurity ions, and slightly larger values when comparing impurities and main ion rotation. For the example discharge shown in the next section, the toroidal rotation difference between the main ion and the measured neon is expected to be of the order of a few tens of $\text{km}~\text{s}^{-1}$ , while the difference between tungsten or nickel turns out to be a only a few $\text{km}~\text{s}^{-1}$ , i.e. less than a per cent of the measured toroidal rotation and therefore negligible.
3 Example discharge
The discharge chosen to explain the method is a neon-seeded hybrid discharge 90279. This is a 1.4 MA, 1.8 T pulse, with 16 MW NBI heating and Ne seeding (blue trace in figure 2 b) starting before the main NBI heating is ramped-up (red trace in figure 2 b). It exhibits slow but steady electron density peaking in the first half of the flat top (figure 2 c), accompanied by strong impurity peaking (figure 2 e–g) and erosion of the central electron temperature (figure 2 d). The value of $Z_{\text{eff}}$ increases strongly in these first seconds (figure 2 h), the total radiated power from the bulk plasma increases slightly (black in figure 2 b) and the plasma stored energy is slightly eroded (figure 2 a), but the discharge nonetheless survives up to the end of the programmed flat top. This discharge exhibits fishbone activity in time range ${\sim}[44.7,45.3]~(\text{s})$ , then saturated $1/1$ modes until $46.2~(\text{s})$ , but no sawtooth cycling, and a $3/2$ mode appearing at $7.3~(\text{s})$ . The absence of mode $1/1$ activity later in the pulse is attributed to modifications in the current density profile with $q(0)>1$ as a consequence of the hollowing of the electron temperature profiles driven by impurity accumulation (Pucella et al. Reference Pucella, Giovannozzi, Challis, Chomiczewska, Giroud, Hobirk, Joffrin, Kappatou, Keeling and King2019).
The first two seconds of the flat top ( $4.5{-}6.5$ ) during impurity accumulation are of interest here for the purpose of explaining the analysis methodologies. Three time points have been chosen along this accumulation path: $t=5.17,5.85,6.17~\text{s}$ (vertical dashed lines in figure 2). All quantities used in the analysis are mapped on the EFIT equilibrium reconstruction accounting for a 3 cm shift necessary to match the HRTS electron temperature at the separatrix to 100 eV. This shift is applied not only to HRTS, but to all diagnostic LoS and measurement positions.
Ion temperature and toroidal rotation are taken from CXRS measurements of $Ne\,X~5249$ (Å), with a time resolution of 50 (ms) and covering the whole radial range (figure 3 b,d). The HRTS diagnostic is used for electron density and temperature profiles, with a time resolution of 50 (ms). Its radial profile does not reach the plasma centre (figure 1), but the density peaking and the decrease in central temperature for the later time point are still detected (figure 3 c). This is confirmed when comparing with LIDAR Thomson scattering data which measure up to the plasma centre but at a low time resolution of 250 (ms) (circles in figure 3 c). The differences between HRTS and LIDAR data are first of all due to different measurement times of the two diagnostics (label in figure 3 a). Especially for the last time point considered (6.17 s, shown in red) when the impurity accumulation has progressed, increasing the central radiation (red in figure 2 f) and reducing further the central electron temperature (red in figure 2 d). The remaining difference, with LIDAR values approximately $10\,\%$ lower across the whole radial range, is instead probably due to uncertainties in the equilibrium reconstruction. When performed without internal constraints, EFIT is known to overestimate the Shafranov shift which will affect LIDAR more than HRTS since it measures closer to the mid-plane (green diamonds in figure 1). The effect of these uncertainties on the final result is anyway minimal because the error on the electron profile fits is ${\sim}6\,\%$ , i.e. roughly of the same order of magnitude.
The 2-D SXR emissivity maps resulting from the inversion routine for these three time points are shown in figure 4(a–c). The back LoS-integral of these poloidal maps compares well with the experimental data for all 28 LoS of SXR camera V at all three time points considered (figure 4 d). A cut at the mid-plane (figure 4(e), positive $\unicode[STIX]{x1D70C}$ corresponding to LFS, negative to HFS) reveals an order of magnitude increase in central emissivity and a slight LFS asymmetry very similar for all time points. For the estimation and propagation of the experimental uncertainties from the SXR LoS-integrals to the inverted emissivity profiles, from the electron temperature to the cooling factors and the final propagation to the resulting high-Z impurity density, the methodologies described in depth in §§ IIB and II of Sertoli et al. (Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018) have been applied.
Tungsten is used as primary high-Z impurity ( $Z_{0}$ ) and two low-Z impurities are included from the start: beryllium as constant background ( $Z_{2}$ ) and the seeded neon left free to evolve in time ( $Z_{1}$ ). The Be concentration has been set to $2.0\,\%$ to match the $Z_{\text{eff}}$ value at 4 s before the increase in effective charge takes place (figure 2 d). The horizontal $Z_{\text{eff}}$ measurement ZEFH has been chosen because it is thought to be less affected by reflections on PFCs that can lead to an artificial increase of the measured value. As a further consistency check, the analysis has also been performed using the vertical LoS measurement ZEFV and the results will be reported in § 3.7. The statistical uncertainties on these measurements are estimated to be ${<}5\,\%$ , including the propagation of electron density and temperature uncertainties used for the calculation, so the difference between the two measurements is outside of the confidence interval.
With a stepwise approach, including more impurities in the mix, checking the consistency between diagnostics and trying to falsify assumptions or testing the trustworthiness of different measurements, four cases have been explored:
(i) W as primary ( $Z_{0}$ ), re-normalized to the VUV concentration measurement $c_{W,qc}$ ;
(ii) step 1. & W density scaled to match the most central bolometer LoSs;
(iii) step 1. & Ni as secondary mid-Z ( $Z_{3}$ ) scaled to match bolometer measurements;
(iv) Ni as primary ( $Z_{0}$ ), SXR multiplication factor $M=3.0$ ;
Case (i) represents the standard analysis, where the W density is assumed to be the only high-Z impurity in the plasma and the VUV measurement of the W concentration is used as cross-calibration for the initial results. In case (ii), the VUV measurement is deemed untrustworthy and the W density profile is further re-scaled so that the total radiation matches what observed along the most central LoSs of both bolometer cameras H and V. The extrapolation of the W density beyond the range of validity of the analysis ( $\unicode[STIX]{x1D70C}_{\max }\sim 0.6$ ) is performed for all cases following the shape of the electron density profile.
For case (iii), if W is not the only mid-/high-Z impurity in the plasma and the VUV measurement is trustworthy, nickel is included in the mix and its absolute value scaled so that the simulated total radiated power including all ions matches the bolometry LoS integrated measurements. Nickel, iron as well as copper are known to be present in JET plasmas and are routinely identified by VUV survey spectrometers. Nickel and Iron have been seen to correlate with the use of the ICRH antennae (Czarnecka et al. Reference Czarnecka, Zastrow, Rzadkiewicz, Coffey, Lawson and O’Mullane2011), while copper with NBI heating, its influx caused by the interaction of fast NBI neutrals with the NBI duct scraper. Due to the very similar mass and charge of these elements, nickel is used as a proxy for mid-Z impurities owing to the availability of atomic data and cooling functions.
Finally, case (iv) turns the problem upside-down, exploring what happens if W has been erroneously chosen as primary impurity and Ni is the main radiator. In order to better understand the consequences of the above assumptions and visualize the main differences on the results and consistency checks, the first three cases will be discussed and shown in parallel (figures 5 and 6). The fourth will instead be shown at the end of this section as final confirmation that case (iii). is the best solution.
3.1 Effects on Zeff
The different assumptions for the impurity content lead to noticeable changes in the contribution to the $Z_{\text{eff}}$ LoS integrated measurement (figure 5 a). The low-Z impurities (Be + Ne) are in general the major contributors (short dashes). Tungsten contributes little because of its low concentration (continuous lines in figure 5 c), reaching a maximum of $\unicode[STIX]{x0394}Z_{\text{eff}}\sim 0.2$ if its density is re-scaled to fill in for the missing radiated power (case (ii)). When nickel is included (case (iii)), it becomes a major contributor towards the end of the accumulation process, accounting for approximately half of the measured LoS-integrated value. The neon concentration (continuous red line in figure 5 b) is therefore lowest in case (iii) (approximately a factor 2), having to account for less $Z_{\text{eff}}$ than in the other two cases. When not including nickel, the match of the estimated neon concentration with the radially averaged CXRS data (dashed line) is way outside the confidence interval of the CXRS measurement which has been estimated propagating a $15\,\%$ error with the standard deviation of all radial points. With the contribution of nickel (case (iii)), the match is instead extremely good for the whole time range of analysis.
3.2 Effects on total radiation
The flux-surface-averaged W concentration (continuous lines in figure 5 c) reaches a maximum of ${\sim}3{-}4\times 10^{-4}$ in the centre (red) when normalized to the VUV concentration measurement (cases (i) and (iii)) changing slightly if nickel is included in the mix (case (iii)). Double that amount is needed to improve the match with bolometric measurements (figure 5 d) as in case (ii). It is clear from these latter plots that the match of the back LoS-integrals (dashed lines) with the experimental data for three LoS (colour coded) over the whole time range of interest is best for case (iii). The total amount of Ni needed to match the bolometer signals is approximately one order of magnitude larger than that of W (dashed lines, case (iii) figure 5 c).
The consistency check with bolometry is further enhanced comparing all available LoS not viewing the divertor (figure 6 a). This comparison clearly shows that increasing the W density to match the central LoSs does not provide a satisfactory match neither for horizontal LoSs viewing the top and bottom of the plasma, nor for the vertical LoS viewing the HFS. The situation improves considerably when including nickel, with an almost perfect match for all LoS of the vertical camera and a very good agreement for the horizontal camera. The reasons for are that nickel exhibits a lower peaking factor and lower centrifugal asymmetry due to its lower mass and charge (equations (2.6) and (2.11)). This can be seen in the plots of the W and Ni density profiles at mid-plane at the time points of interest for case (iii) (figure 7 a,d). Including also effects from the shape of the cooling factor, with nickel radiating less at higher electron temperatures than tungsten, a global reduction in radiation peaking and an increased radiation on the HFS will take place, improving the match with the bolometer LoSs viewing away from the plasma centre.
3.3 Match with CXRS Ne concentration
The comparison of the estimated Ne concentration with the CXRS profiles (figure 6 b) confirms the good match already seen in the time evolution, but at the same time reveals a peaking in the centre not included in the analysis because of the flat concentration constraint. This experimental point could be an outlier and two independent considerations corroborate this opinion.
The error estimation of the CXRS rotation and temperature measurements relies only on the fit of the spectral lines, while the estimation of the impurity concentration requires knowledge of the beam characteristics including the beam attenuation whose uncertainty is very large close to the plasma centre (Giroud et al. Reference Giroud, Meigs, Negus, Zastrow, Biewer and Versloot2008). Moreover, the most central CXRS radial measurement at $\unicode[STIX]{x1D70C}\sim 0.05$ (not shown here) has be independently excluded from the analysis due to extremely noisy ion temperature and toroidal rotation result. This means that the beam attenuation in this region is already very large and errors in its estimation could lead to large changes in the calculated impurity density.
The second point is that the experimental peaking is much larger than that expected when calculating the Ne peaking using (2.6). Normalizing the profiles to mid-radius, the expected central value should be $c_{Ne}(\unicode[STIX]{x1D70C}=0.15)\sim 0.76$ , $0.75$ and $0.77$ for the three time points respectively. While the difference for the first time point (black) is within the error bars, for the latter two the experimental values are well beyond the $2\unicode[STIX]{x1D70E}$ boundary.
3.4 Match with VUV
Calculating the expected W concentration measurement from VUV spectroscopy and comparing it with the experimental values (figure 6 c), the best match with the quasi-continuum measurement $c_{W,qc}$ (triangles) is obtained only when accounting for nickel contributions (case (iii)). The reason for this is that the presence of nickel accounts for part of the SXR emissivity that was initially ascribed to W, changing the shape of the final W density profile, especially in the later phase of the analysed time range. The match with the spectral line measurement $c_{W,l}$ is instead not optimal for any of the three cases. This is most probably caused by uncertainties in the equilibrium reconstruction: errors in the Shafranov shift will have a large impact on this measurement, but will be more forgiving on the quasi-continuum value which measures further out.
3.5 Match with toroidal rotation
The final consistency check is between the measured CXRS toroidal rotation of $Ne\,X$ and the value estimated from the W density asymmetry modelled inverting (2.11) to extract $\unicode[STIX]{x1D714}_{\unicode[STIX]{x1D719}}$ . This match is relatively good for all cases (figure 6) and this consistency check alone would not be sufficient to distinguish between the three. This is apparent when considering the uncertainties in the W density asymmetry and viewing the problem in the opposite direction comparing the measured W density asymmetry with the expected one estimated using the CXRS toroidal rotation measurements (figure 7 b). It is clear from this plot that the slight differences in asymmetry are all within the confidence interval and therefore cannot be sufficiently discriminated. The errors have been estimated propagating the error of the W density, calculated by propagating the uncertainties of the deconvoluted SXR emissivity ( $5\,\%$ error from the raw SXR data and deviation of the back fit with respect to the data) and those of the cooling factors (estimated from upper and lower estimates of the electron temperature given the diagnostic uncertainties and the standard deviation of data points if time averaging of the raw data is performed). This is clearly a lower estimate, since it does not include uncertainties in either the W atomic data or those of other elements included in the analysis.
3.6 Nickel as main high-Z impurity
As a final confirmation that including nickel in the impurity mix provides the best match to all measurements but that the presence of W is of utmost importance and cannot be neglected, figure 8 shows what happens if nickel is the only mid-/high-Z impurity $Z_{0}$ . Accounting for most of the SXR emission, the Ni contribution to $Z_{\text{eff}}$ dominates the measurement already half-way during the time range of interest (figure 8 a). The Ne concentration therefore decreases, matching relatively well the CXRS measurement up to ${\sim}5~(\text{s})$ , but going outside of the CXRS confidence interval for later time points. The match with the bolometer LoS-integrals (figure 8 d) is marginally good, but still worse than case (iii) (figure 6 a). Finally, the consistency check that clearly falsifies the assumption that Ni is the only mid-/high-Z impurity, is the comparison with toroidal rotation (figure 8 c) where it is clear that the asymmetry in the SXR emissivity is far too large to be ascribed to nickel.
3.7 Impact of other diagnostic uncertainties
Discrepancies between different diagnostics or LoS measurements are known to take place and it is sometimes unclear which one should be discarded and which one retained for the analysis. In this framework, the main discrepancies that have to be addressed are between LIDAR and HRTS for the electron profile diagnostic and between the vertical and horizontal lines of sight of the $Z_{\text{eff}}$ visible bremstrahlung measurement.
Using LIDAR instead of HRTS for the electron profile fits (figure 3 c), due to the slightly lower density, a lower background $Be$ concentration ( $1.5\,\%$ ) is necessary to match the initial measured $Z_{\text{eff}}$ (still using ZEFH). With this change only, the final results for Ne, W and Ni are all recovered to within a few per cent and, since the results are well within the final uncertainties, no relevant information can be provided to discard either of the profile diagnostics.
The situation is slightly more complicated when using the vertical LoS in place of the horizontal one (black and red traces in figure 2 h). The ZEFV measurement is higher by ${\sim}20\,\%$ with respect to ZEFH up to around 6 s (figure 2 h) and well outside of the statistical uncertainty ( ${<}5\,\%$ ). In order to match this $Z_{\text{eff}}$ value before the neon puff, a Be concentration of the order of $6\,\%$ is necessary. Using this value as a starting point leads to results that are very similar to the original case, for both the W and Ni concentrations (figure 9 d) as well as for the W density asymmetry (figure 9 e) and total radiated power (figure 9 f). The only consistency check that fails dramatically is that with the Ne concentration. The neon required to match the $Z_{\text{eff}}$ measurement is approximately a factor 2 higher than the one estimated by CXRS and well outside the confidence interval up to ${\sim}5.8~\text{s}$ . Beyond this time, when nickel starts contributing substantially to $Z_{\text{eff}}$ , the concentration drops, going well below the CXRS estimates. This suggests that the vertical measurement is affected by an unknown systematic uncertainty that is not constant in time. As stated earlier in the paper, reflections on the machine wall could lead to an increased value and could be a possible cause of this discrepancy.
These results therefore confirm the choice of ZEFH as the most trustworthy measurement for the effective charge and underline the importance of multiple consistency checks in an integrated framework for the calculation of the plasma composition. If the independent CXRS measurement of the neon concentration were not available, another way to assess the reliability of the background Be concentration would be to model the neutron rate (e.g. using TRANSP (Ongena et al. Reference Ongena, Voitsekhovitch, Evrard and McCune2012)) which would be affected by the dilution which would increase of $20\,\%$ when increasing the Be concentration from 2 % to 6 %.
4 Conclusions and outlook
The methodologies originally developed to model the intrinsic W density profiles in both ASDEX Upgrade (Sertoli et al. Reference Sertoli, Dux and Pütterich2015) and JET (Sertoli et al. Reference Sertoli, Flanagan, Maslov, Maggi, Coffey, Giroud, Menmuir, Carvalho, Shaw and Delabie2018) have been further expanded to analyse the plasma composition in JET-ILW including four different impurity species simultaneously: two low-Z and two mid-/high-Z elements. This is necessary because JET-ILW plasmas are known to contain a large zoo of elements originating from the main chamber walls (Be), the divertor (W), the NBI duct scraper (Cu), the ICRH limiters (Ni) or injected deliberately as seeding gases (Ne, Ar, N, etc.). Such a complex system has an extremely large number of free parameters, but, as demonstrated here, can be relatively well described with a few simple theory-driven assumptions corroborated by experimental evidence, and a complicated, integrated analysis of multiple diagnostic data.
The different behaviour of the various elements and their unique contribution to the wide range of measurements included in the analysis is in fact the main reason why they can be disentangled: low-Z elements have low radiated power per unit ion, but contribute strongly to the effective charge; high-Z elements radiate orders of magnitude more, but are minor contributors to $Z_{\text{eff}}$ ; mid-Z and high-Z elements can be distinguished by their poloidal asymmetries. All of these quantities have to be balanced in order to provide an unambiguous result of the plasma composition.
In the example JET-ILW Ne-seeded hybrid discharge reported here, the observed SXR emission, the W concentration measured by passive VUV spectroscopy, the LoS $Z_{\text{eff}}$ measurement, the observed poloidal asymmetry of the SXR emission, the CXRS Ne density and the LoS integrals of the total radiation as measured by bolometry could all be matched including simultaneously Be, Ne, Ni and W. Using a stepwise approach to increase the analysis complexity, attempting to falsify potentially inaccurate measurements, using different background profile diagnostic data and initial assumptions, the final results have been demonstrated to be relatively robust. It has also been proven that data from a few diagnostics are often not enough to distinguish between various possible solutions and can lead to erroneous conclusions which can propagate detrimentally downstream if used for further analysis and modelling.
Of the ${\sim}50$ JET-ILW discharges analysed up to now with this method, around $30$ have converged to consistent results for all diagnostics. The remaining $20$ show good results but do not satisfy all consistency checks simultaneously. The reasons for this could be systematic errors in the measurements (e.g. faults in the data acquisition) or contamination from unaccounted impurities (e.g. mixed impurity seeding with N $_{2}$ and Ar). Changes in engineering parameters such as variations in gas puff or heating power could also be the cause of varying impurity sources which would lead to inconsistencies in the results with the present assumptions. A temporary and perhaps un-elegant solution would be to analyse such phases separately, trying to match the background conditions as closely as possible to the transition.
These limitations suggest possible future enhancements. Information on the sources could be added to avoid the approximation of self-similar and identical time evolution of the sources. Coupling the analysis with fast transport solvers could give an estimate of the ion temperature screening term in (2.5) presently neglected when re-scaling the secondary mid-Z impurity density peaking. This coupling would furthermore enable the use of transport-dependent ionization balance and cooling functions. LIE used in this publication is known to be trustworthy for mid-/high-Z elements in the plasma core but not in the pedestal region (see e.g. Asmussen et al. (Reference Asmussen, Fournier, Laming, Neu, Seely, Dux, Engelhardt and Fuchs1998) and Kallenbach et al. (Reference Kallenbach, Bernert, Dux, Casali, Eich, Giannone, Herrmann, McDermott, Mlynek and Müller2013)) where this approximation could lead to underestimate the impurity density and total radiated power (Kallenbach et al. Reference Kallenbach, Bernert, Dux, Casali, Eich, Giannone, Herrmann, McDermott, Mlynek and Müller2013, figure 1). If the results of this analysis are to be used in simulations or modelling of particle and heat transport or ELM stability, where the profile shape in the pedestal can change the results dramatically, the confidence in results in the pedestal region has to be increased.
Despite the challenges in accurately determining the plasma composition, these measurements are of prime importance for present-day and future magnetic-controlled fusion devices with multi-material PFCs. Knowledge of the radial profiles of impurity densities, effective charge and total radiated power are key parameters to correctly understand and model current experiments, and thus also to extrapolate such results to future machines and reactors. Due to the complexity of such measurements, simple assumptions are frequently used to proceed with the transport simulations. These crude approximations can lead to an erroneous calculation of important parameters such as main ion dilution, current density profile and power balance, which propagate further to the estimation of neutron rates, particle and heat transport, turbulence and MHD stability analyses. The methodologies explained in this paper are currently being applied to a variety of discharges to check the entity of these effects and results will be soon reported in a separate publication.
Acknowledgements
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement no. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The authors would also like to thank G. Pucella, E. Giovannozzi, C. Bourdelle, C. Maggi, K. Lawson, I. Coffey, T. Pütterich and A. Czarnecka for the fruitful discussions and feedback.