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Gyrokinetic and kinetic-MHD simulations are performed for the fishbone instability in the DIII-D discharge #178631, chosen for validation of first-principles simulations to predict the energetic particle (EP) transport in an ITER pre-fusion baseline scenario. Fishbone modes are found to generate zonal flows, which dominate the fishbone saturation. The underlying mechanisms of the two-way fishbone-zonal flows nonlinear interplay are discussed in details. Numerical and analytical analyses identify the fishbone-induced EP redistribution as the dominant generation mechanism for zonal flows. The zonal flows modify the nonlinear dynamics of phase space zonal structures, which reduces the amount of EPs able to resonate with the mode, leading to a lower saturation amplitude. Simulation results including zonal flows agree quantitatively with DIII-D experimental measurements of the fishbone saturation amplitude and EP transport, supporting this novel saturation mechanism by self-generated zonal flows. Moreover, the wave-particle mode-locking mechanism is shown to determine quantitatively the fishbone frequency down-chirping, as evident in GTC simulation results in agreement with predictions from analytical theory. Finally, the fishbone-induced zonal flows are possibly responsible for the formation of an ion internal transport barrier (ITB) in the DIII-D discharge. Based on the low EP transport and the large zonal flow shearing rates associated with the fishbone instability in gyrokinetic simulations of the ITER scenario, it is conjectured that high performance scenarios could be designed in ITER burning plasmas through fishbone-induced ITBs.

In magnetic fusion devices, error field (EF) sources, spurious magnetic field perturbations, need to be identified and corrected for safe and stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out to test the portability of the novel non-disruptive method, designed and tested in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007), and to perform an assessment of model-based EF control strategies towards their applicability in ITER. In this paper, the lessons learned, the physical mechanism behind the magnetic island healing, which relies on enhanced viscous torque that acts against the static electro-magnetic torque, and the main control achievements are reported, together with the first design of the asynchronous EF correction current/density controller for ITER.

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 phase and exit phase of the ITER 15 MA/5.3 T DT scenario. The modelling utilizes the recently implemented option to treat deuterium and tritium separately in the SOL/divertor, enabling a consistent treatment of deuterium and tritium in the whole plasma volume, which is a unique capability of JINTRAC. In addition, these are the first JINTRAC simulations of this scenario that use a first-principles transport model to self-consistently model the ECRH power deposition and to include tungsten while keeping track of tungsten sputtering and accumulation. The flat-top simulations demonstrate the possibility of sustaining a steady state fusion Q of 10 using pure deuterium gas puffs together with DT mixed pellets, which is an option to make a more effective use of tritium. Simulations of the exit phase are set up sequentially, with each phase providing initial conditions for the next, starting with a density decay at full current and auxiliary power, and demonstrate the possibility of reducing the density robustly within a few seconds. Following the density decay, a subsequent auxiliary power ramp-down in H-mode is performed with a late H–L transition at low auxiliary power, which may provide an option for the optimization of the plasma termination. The final ramp-down phase consists of a current ramp-down in L-mode to 3.75 MA.

ObjectivesTo determine if adapting a widely-used triage scale into a computerized algorithm in an electronic health record (EHR) shortens emergency department (ED) triage time.DesignBefore-and-after quasi-experimental study.SettingUrban, tertiary care hospital ED.ParticipantsConsecutive adult patient visits between July 2011 and June 2013.InterventionA step-wise algorithm, based on the Emergency Severity Index (ESI-5) was programmed into the triage module of a commercial EHR.Main outcome measuresDuration of triage (triage interval) for all patients and change in percentage of high acuity patients (ESI 1 and 2) completing triage within 15 min, 12 months before-and-after implementation of the algorithm. Multivariable analysis adjusted for confounders; interrupted time series demonstrated effects over time. Secondary outcomes examined quality metrics and patient flow.ResultsAbout 32 546 patient visits before and 33 032 after the intervention were included. Post-intervention patients were slightly older, census was higher and admission rate slightly increased. Median triage interval was 5.92 min (interquartile ranges, IQR 4.2-8.73) before and 2.8 min (IQR 1.88-4.23) after the intervention (P < 0.001). Adjusted mean triage interval decreased 3.4 min (95% CI: -3.6, -3.2). The proportion of high acuity patients completing triage within 15 min increased from 63.9% (95% CI 62.5, 65.2%) to 75.0% (95% CI 73.8, 76.1). Monthly time series demonstrated immediate and sustained improvement following the intervention. Return visits within 72 h and door-to-balloon time were unchanged. Total length of stay was similar.ConclusionThe computerized triage scale improved speed of triage, allowing more high acuity patients to be seen within recommended timeframes, without notable impact on quality.

The fauna of Dolichopodidae in the Arkhangelsk Region was studied sporadically and currently in-cludes 50 species. Onezhskoye Pomorye National Park (Arkhangelsk Region, Russia) was established in 2013 to protect the pristine forests and coastal ecosystems of the hardly accessible territories along the White Sea coast of the Onega Peninsula. The insect fauna of the National Park was almost un-known until recently, with only 17 Diptera species from the Culicidae and Chironomidae families listed in the online cadaster. During the short expedition to Onezhskoye Pomorye National Park in July–August 2020, more than 350 Dolichopodidae specimens were collected with yellow pan traps and sweep netting on routes that mainly passed through coastal habitats. Nineteen species of Dolichopodi-dae have been reported for the first time from this territory. Thirteen species are reported for the first time from the Arkhangelsk region, bringing the total number of known species to 63. The species list is given and supplied with brief comments on habitat and distribution. Photos of some typical habitats are provided. Most of the discovered species are widespread throughout the Palaearctic Region. Rarer species include Dolichopus diadema, which probably represents a southern Palaearctic element, and Hydrophorus norvegicus, which was previously known only from Fennoscandia.

The dynamics for the transition from L-mode to a stationary high Q DT H-mode regime in ITER is expected to be qualitatively different to present experiments. Differences may be caused by a low fuelling efficiency of recycling neutrals, that influence the post transition plasma density evolution on the one hand. On the other hand, the effect of the plasma density evolution itself both on the alpha heating power and the edge power flow required to sustain the H-mode confinement itself needs to be considered. This paper presents results of modelling studies of the transition to stationary high Q DT H-mode regime in ITER with the JINTRAC suite of codes, which include optimisation of the plasma density evolution to ensure a robust achievement of high Q DT regimes in ITER on the one hand and the avoidance of tungsten accumulation in this transient phase on the other hand. As a first step, the JINTRAC integrated models have been validated in fully predictive simulations (excluding core momentum transport which is prescribed) against core, pedestal and divertor plasma measurements in JET C-wall experiments for the transition from L-mode to stationary H-mode in partially ITER relevant conditions (highest achievable current and power, H 98,y ∼ 1.0, low collisionality, comparable evolution in P net/P L-H, but different ρ ∗, T i/T e, Mach number and plasma composition compared to ITER expectations). The selection of transport models (core: NCLASS + Bohm/gyroBohm in L-mode/GLF23 in H-mode) was determined by a trade-off between model complexity and efficiency. Good agreement between code predictions and measured plasma parameters is obtained if anomalous heat and particle transport in the edge transport barrier are assumed to be reduced at different rates with increasing edge power flow normalised to the H-mode threshold; in particular the increase in edge plasma density is dominated by this edge transport reduction as the calculated neutral influx across the separatrix remains unchanged (or even slightly decreases) following the H-mode transition. JINTRAC modelling of H-mode transitions for the ITER 15 MA / 5.3 T high Q DT scenarios with the same modelling assumptions as those being derived from JET experiments has been carried out. The modelling finds that it is possible to access high Q DT conditions robustly for additional heating power levels of P AUX 53 MW by optimising core and edge plasma fuelling in the transition from L-mode to high Q DT H-mode. An initial period of low plasma density, in which the plasma accesses the H-mode regime and the alpha heating power increases, needs to be considered after the start of the additional heating, which is then followed by a slow density ramp. Both the duration of the low density phase and the density ramp-rate depend on boundary and operational conditions and can be optimised to minimise the resistive flux consumption in this transition phase. The modelling also shows that fuelling schemes optimised for a robust access to high Q DT H-mode in ITER are also optimum for the prevention of the contamination of the core plasma by tungsten during this phase.

Improving the efficiency of the sheep industry is based not only on additional investments, but also on the use of modern methods of breeding and selection. A significant role is given to modeling and forecasting processes in sheep breeding. The article is devoted to the development of a model for the growth and development of lambs in the first months of their post-embryonic period, which contains a system of equations describing the energy, protein and nutritional needs of animals. This model takes into account the influence of environmental factors on the growth and development of lambs and the features of the formation of future productivity.

Limoniidae is one of the most species rich Dipteran families, with 661 reported species in Europe. Despite the fact that the European limoniid crane fly fauna has been studied ever since Carolus Linnaeus, it is still poorly known.In this study we summarize the taxonomic and faunistic studies of European Limoniidae, which described new species and reported first country records, between 2010 and 2020. We also report occurrence data of 237 Limoniidae species which represent the first country records or conformational records from various European countries, as we report eight species from Albania, one from Austria, thirty-seven from Belarus, five from Belgium, two from Bulgaria, two from Estonia, six from Finland, seven from France, fourteen from Greece, seventeen from Hungary, two from Iceland, six from Italy, eleven from Latvia, one from Malta, nine from Montenegro, two from the Netherlands, ten from North Macedonia, forty-two from Norway, one from Poland, five from Portugal, twenty from Romania, thirty-eight from Serbia, one from Slovenia, five from Spain, and seven species from Sweden for the first time. From the European territory of Russia we report twenty-eight species from Central European Russia, seventy-three from East European Russia, fifteen from North European Russia, one from Northwest European Russia and seven from North Caucasus for the first time. Confirmatory records and corrigenda are also included.

For the first time, amorphous TiO2 aerogels with a high specific surface area (420 m2/g) and low geometric density (~0.1 g/cm3) were obtained using epoxide-induced gelation in N,N-dimethylformamide. Impregnation of the resulting aerogels with aqueous solutions of H2PtCl6 and NaBH4 followed by thermal annealing made it possible to obtain Pt/TiO2 photocatalysts, which showed very high activity for titanium dioxide–based aerogels in the generation of hydrogen from aqueous alcohol solutions (~5 h–1 g–1). [ABSTRACT FROM AUTHOR]

Fungus gnats represent an informal assemblage of insect families in the superfamily Sciaroidea. This is a highly diverse group comprising nearly 1000 species in Fennoscandia. Fungus gnats are comparatively well studied in the Republic of Karelia, although the coverage is uneven. Hence, any new data from poorly known areas would provide a better background for further analysis of zoogeographical patterns both at local and at Fennoscandian level. With just 100 known species, the fauna of fungus gnats in the Kostomuksha State Nature Reserve has until recently been insufficiently studied. The paper presents the results of faunistic research in the Kostomuksha State Nature Reserve since 1993. The revised checklist is based on original material and includes 177 species of fungus gnats belonging to the families Bolitophilidae, Diadocidiidae, Keroplatidae and Mycetophilidae. Eighty-five species were added to the fauna, and eight species were removed from the list. The revealed diversity is comparatively low and most of the recorded taxa are common in Fennoscandia. However, a number of rare and remarkable species was found, indicating a potentially rich fauna. Five species (Mycomya obliqua, Sciophila krysheni, Syntemna morosa, Mycetophila devioides, Mycetophila haruspica) are reported for the first time from the Republic of Karelia and Russia. Mycomya obliqua is also new for the Palaearctic region. All remarkable records are commented, and male genitalia images are provided for poorly known species. Two species of presumably western origin (Sciophila krysheni and Mycetophila devioides) and one Nearctic species (Mycomya obliqua) are discussed in more details. A relatively low diversity is explained by an insufficient earlier collecting activity and concentration of recent Malaise trapping on small islands with a poorer fauna. The need for further studies in the Kostomuksha State Nature Reserve, with a better coverage of habitats and using additional collecting methods, is substantiated.

The superfamily Tipuloidea contains the following cranefly families: Cylindrotomidae, Limoniidae, Pediciidae and Tipulidae, with 1267 species known in Europe. Recent studies have increased our knowledge regarding these families substantially, but craneflies still represent an understudied group, even in Europe. A previous paper focused on European Limoniidae, summarizing the faunistic and taxonomic papers concerning the family between 2010 and 2020, and reported additional new country records. In this study, the focus is on the other three cranefly families: Cylindrotomidae, Pediciidae and Tipulidae, summarizing taxonomic and faunistic studies concerning these families in Europe between 2010 and 2022. Also presented are 204 occurrence records belonging to one Cylindrotomidae, 23 Pediciidae and 62 Tipulidae species, which represent first country records from various European countries: three from Albania, three from Belarus, one from Belgium, three from Bosnia and Herzegovina, 13 from Bulgaria, two from Cyprus, two from Denmark, three from Estonia, one from Finland, two from Greece, three from Italy, one from Montenegro, one from North Macedonia, six from Norway, six from Poland, four from Portugal, seven from Serbia, four from Slovenia, two from Spain and one from Sweden, and three from the European territory of Russia. In addition of species known already from Russia, six are presented as new from Central European Russia, 26 from East European Russia, six from North Caucasus and six from North European Russia.

The pre–fusion power operation 1 phase of ITER is planned to be characterized by electron cyclotron resonance heating only. Under the assumption that the access to H–mode is determined by a critical ion heat flux at the plasma edge, full–radius ASTRA simulations with the TGLF–SAT2 transport model are performed in order to compute the ion heat flux produced by the thermal exchange between electrons and ions in different operational conditions. Both hydrogen and deuterium plasmas at 5 MA are considered, respectively at 1.8 T and 2.65 T, corresponding to one third and half of the nominal maximum magnetic field. Different levels of electron cyclotron heating power are considered in sets of simulations with increasing values of the electron line averaged density. The predictions are compared with the currently available scaling of the critical ion heat flux. In hydrogen, 20 MW of electron heating power are predicted to allow H–mode access in a vanishingly small density window, whereas 30 MW and 40 MW would allow more substantial H–mode operational windows. Despite the fact that in deuterium plasmas the thermal exchange between electrons and ions is smaller by the hydrogen to deuterium mass ratio compared to hydrogen plasmas, the lower H–mode power threshold in deuterium leads to the prediction that an even broader and more robust domain to access H–mode is obtained at half field at 40 MW in deuterium as compared to operation in hydrogen at one third of the maximum magnetic field, even at the same power.

The as-built stiffness in the ITER central solenoid (CS) modules (CSM1 thorough to CSM4 are currently manufactured) determines the range of vertical compression forces that can be tolerated by the CS modules during ITER operation. Since the as-built stiffness of the CS modules manufactured (∼32 GPa and ∼34 GPa for CSM1 and CSM2, respectively and similar for the other modules) has been reduced from the design value (53 GPa), the CS axial (vertical) force criteria have been updated assuming a conservative stiffness (25 GPa) with margins for all six CS modules. Initial analysis using the updated CS force criteria has revealed that this reduction affects only the plasma initiation with fully charged CS in the ITER 15 MA Baseline DT scenario, resulting in a slight reduction of poloidal magnetic flux, from 117.5 Wb to 116.2 Wb at initial CS magnetization. Therefore, the 15 MA Baseline scenario has been re-developed with an updated plasma start-up, and then the entire evolution of the CS and poloidal field coil parameters has been validated against all the coil currents, fields and forces criteria. To explore potential risks and opportunities for further optimization of scenarios, the equilibrium operational space (the plasma internal inductance versus the poloidal magnetic flux produced by the coils) at flat-top burn has been analyzed using the CORSICA and DINA codes. The three major ITER reference DT operation scenarios, 15 MA Q = 10 Baseline, 12.5 MA Q > 5 Hybrid and 10 MA Q ∼ 5 Steady-State, satisfy all the coil criteria including the CS force updated reflecting the as-built stiffness. The evolution of the plasma discharge parameters within the equilibrium operational spaces provided a guidance for potential optimization with margins.

Pellet injection is the most promising technique to achieve efficient plasma core fuelling, key for attaining stationary scenarios in large magnetic confinement fusion devices. In this paper, the injection of pellets with different volumes and speeds into standard plasma scenarios in ITER (tokamak) and Wendelstein 7-X (stellarator) is studied by modeling the pellet ablation and particle deposition, focusing on the evaluation of the expected differences in pellet plasmoid drifts in tokamaks and stellarators. Since the efficiency of the damping-drift mechanisms is predicted to depend on the magnetic configuration, device-specific characteristics are expected for the temporal evolution of the plasmoid drift acceleration. For instance, plasmoid-internal Pfirsch–Schlüter currents dominate the drift damping process for stellarators, while plasmoid-external currents are more relevant for tokamaks. Also, relatively larger drifts are in principle expected for W7-X due to higher field gradients in relation to machine dimensions. However, shorter plasmoid-internal charge reconnection lengths result in the drift damping due to internal Pfirsch–Schlüter currents being more effective than in a tokamak. Therefore, the average relative drift displacement during the whole plasmoid homogenization may a priori be comparable in both magnetic configurations. Moreover, High Field Side (HFS) injection is expected to be highly advantageous to maximize pellet particle deposition in ITER, whereas it may only be beneficial in medium to high β environments in W7-X. Finally, there may be means for the optimization of pellet injection configurations in both ITER and W7-X for the considered plasma scenarios despite the sizeable differences in the relative importance of the mechanisms of plasmoid drift acceleration and deceleration in play.

Long Pulse Scenarios (LPS) in ITER foreseen during the Pre-Fusion Power Operation (PFPO) phase of the ITER Research Plan (IRP) are assessed using 1.5D transport simulations within the ASTRA framework. Such assessment is required to predict the operational space for LPS operation in PFPO, as well as to evaluate which physics processes for LPS operation during Fusion Power Operation (FPO) could be studied during PFPO. An important aspect in the development of LPSs in PFPO is to minimize lifetime consumption of the Central Solenoid (CS) for these scenarios. The maximum pulse length achievable for LPSs in PFPO with no consumption of CS lifetime (currents in CS coils ⩽30 kA per turn) has been assessed for a range of heating schemes and heating mixes, confinement regimes (L-mode and H-mode) and for helium and hydrogen plasmas. The operational space of LPS and pulse length has been explored through density scans with the Heating and Current Drive mix required for the FPO Q ⩾ 5 steady-state plasma scenario (namely Neutral Beam Injection and Electron Cyclotron Heating) including acceptable shine through losses on the first wall for both helium and hydrogen plasmas. Fast particle physics aspects that are common between FPO plasmas and LPS PFPO H-mode plasmas at low densities are studied including MHD stability analysis with the KINX code and non-perturbative critical gradient model based on high-n Toroidal Alfven Eigenmodes (TAE) stability kinetic ballooning code HINST calculations.

The ITER Radial Gamma-Ray Spectrometer (RGRS) consists of three gamma-ray detectors observing the plasma through three collimated, coplanar, radial lines of sight (LoS). The system was initially designed to monitor the runaway electron emission and the alpha-particle density profile [Nocente et al., Nucl. Fusion 57, 076016 (2017)]. This work presents a novel technique for measuring the fusion power during D-T operation using the RGRS. This method is based on the absolute measurement of the 17 MeV fusion gamma-rays and a semi-analytical computation of their transport from the plasma source to the detectors. This approach was initially developed and tested at JET during the second D-T campaign (DTE2) on a single LoS diagnostic [Dal Molin et al., Phys. Rev. Lett. (submitted) (2024); Rebai et al., Phys. Rev. C (submitted) (2024); and Marcer et al., Nucl. Fusion (unpublished) (2024)]. This work exploits the multiple LoS of the RGRS to create a combined virtual diagnostic whose detected fraction of the total plasma emission is less affected by variations in the plasma emission profile, reducing systematic uncertainties on the estimated total emission, compared to the individual detectors. [ABSTRACT FROM AUTHOR]