Strengthening Nuclear Fusion Research in Romania SNFR-RO

The aim of the project is to strengthen the participation of the Romanian teams in the EUROfusion project, by improving the hardware equipment, developing the research facilities, and increasing the team integration. Achieving these objectives will allow to obtain significant advances in the work related to the following EUROfusion WPs: WPPWIE, WPMAT, WPPRD, WPMAG, WPBB, WPTE, WPSA.

In thje framework of the WPBB related activities, one of the objcetives was to develop a procedure to produce tritiated samples with different activity levels and to develop an experimental set-up to monitor the release behavior of the tritium from materials relevant to nuclear fusion. The experiments were conducted as a collaboration between the Low-Temperature Plasma Department in INFLPR responsible for the qualitative detection of tritium release and the Radioisotopes and Radiation Department from IFIN-HH for sample tritiation.

Tungsten samples deposited on a molybdenum substrate were produced and analyzed using the HiPIMS technique. These samples were exposed to tritium and tritium desorption was monitored and analyzed using thermal desorption spectroscopy (TDS). Before measuring the tritium in the tungsten samples, a calibration was performed to accurately determine the T quantity, using deuterium and hydrogen, as direct calibration with T2 is not possible for safety reasons. After calibration, the amount of tritium released from the analyzed samples was measured by heating them up to 1325 K. It was observed that desorption begins at high temperatures, around 450°C, and the desorption profile is broad, encompassing different trapping and release mechanisms for tritium. A main peak was observed at 550°C, followed by another peak with maximum intensity at 700°C. The analysis suggests that tritium is absorbed through the surface, with diffusion playing a significant role in the desorption profile, and tritium being trapped in energetically favourable sites, such as vacancies or defects in the material.

Another objective was to produce W-O coatings by using HiPIMS High Power Magnetron Sputtering deposition. The HiPIMS power supply was purchased by using the funds of the present project. W-O Coatings with thickness in the range 1.3-3.2 µm and oxygen concentrations between 1.7 at.% and 8.5 at.% were produced and analyzed.

Also, in connection with the future work for WPPWIE, a laser scattering system suitable for optical diagnostics of in-flight W nanoparticles was designed, implemented, and tested. This system is useful for investigation of the W dust mobilization from surfaces placed in a vacuum chamber, under the action of gas flows or electric fields. A dedicated vacuum chamber was designed and the necessary vacuum pumps and components were acquired leading to a performant experimental setup adequate for the synthesis of W dust in controlled conditions simultaneously with the in-situ optical diagnostics of dust transport.This system is useful for obtaining details on the stability of W surfaces in relation to exposure to oxidizing molecules (oxygen, water vapor) inherent as impurities or present in the Tokamak due to accidental contaminations, under high temperature conditions. The configured system consists of associating temperature-controlled sublimation sources with methods for evaluating the sublimation process, either by chemical analysis of deposits collected on dedicated substrates, or by detecting sublimated species by mass spectrometry.

In the framework of WPMAT detailed numerical simulations concerning material properties simulations have been performed.  Thermo-calc software was developed based on CALPHAD approach and together with appropriated thermodynamic databases can be used to predict the material behaviour during its life cycle. The simulations predict reasonably well the phase equilibria in a wide temperature range when compared with available literature data. It is a tool that shortens the experimentation time and reduces the consumption of materials. However, it cannot eliminate experimental validation. Based on the present (preliminary) data, it can be appreciated that the application potential of the four HEA alloys is as follows (considering the fifth alloying element): Zr > Ta > Nb > Ti. CALPHAD was used to investigate W-Ta-V-Fe-Ti system, the Cu-(Fe,Ta,Ti,W) thermal barriers materials and CuCrFeV (Ti, Ta, W, Mo) new materials. All these materials are also experimentally investigated in the frame of EUROfusion work and therefore we can evaluate the accuracy of the CALPHAD modelling versus the experimental findings, as well as with other possible modelling approaches. A powder metallurgy route was developed and used to produce Cu_x-CrFeVTi HEA alloys which are investigated as precursors for the Cu-rich part of a W-Cu FGM. The possibility to produce in INCDFM by mechanical alloying route HEA powders was also tested. The powder compositions were determined by thermodynamic simulations using the new software acquired within this project (see B1 task report). W-HEA composites have been consolidated by SPS and Vickers hardness investigations shows that at low concentrations the values of pure W material are preserved. The electron irradiation facility in INFLPR was upgraded to increase the electrons fluence calculations and thus allowing for more efficient experiments.

To support the activities within WPMAT, but of equal importance to WPMAG, societal attention has been given to X-ray imaging methods for complete assessments of microstructural integrity and compositional mapping in materials, components, and processes relevant to nuclear fusion. Investigative imaging techniques have improved with the implementation of dual-energy X-ray combined microtomography (DEXCT), microbeam X-ray fluorescence (microXRF), and thermal wave nondestructive testing (TWNT). These upgrades are critical in increasing the accuracy and capabilities of our imaging methodologies.

In the framework of WPBB, for the development of the HCPB breading blanket, the 2D and 3D modelling software acquired, additional to the existing software enhanced the capability for 2D and 3D system modelling and drawing management to design and construct various experimental rigs for material characterization for the development of the Tritium extraction and recovery (TER) system for DEMO HCPB. In addition, using the add-on PIE software for CATIA, a new 3D concept for the TER system had been developed based on the evolution of the R&D program for TER development. An existing experimental rig has been enhanced with sensors, pumps, and fittings in order to investigate the formation of oxides on samples of relevant materials for the construction of the HCPB TER system, like stainless steel and EUROFER 97. The investigations had the main goal to observe the formation of chromium oxide on samples subject to conditions relevant for the HCPB BB tritium extraction and removal system. The results show that on both types of samples (SS and EUROFER97), chromium oxides are being formed, but in less amount on EUROFER samples. So far, the oxides seem stable, but tests will continue for longer periods, in order to identify the evolution over time.

Several computation power enhancements have been achieved for the work on WPTE and WPSA. They allowed to prove that the detection of hidden transitions in the Mode Locked (ML) time series before disruptions by information content variations and by using certain statistical indicators (skewness, climacogram) could be a useful tool for identifying the time interval when distinctive features related to the coming disruptions are available.

 Another subject related to WPTE is the understanding and the prediction of turbulent transport in tokamak devices. This could be achieved using a large database of transport coefficients derived for many plasma parameters. Unfortunately, this requires a large CPU effort beyond our present capabilities. In view of attaining this purpose in the future stages of the project, new parallelization procedures have been implemented in the numerical transport codes as well as new distribution strategies for total workload. In conjunction with future hardware CPU acquisitions, these improvements should allow us to successfully model the turbulent transport for our Eurofusion-related tasks. The team made use of its newly acquired hardware capabilities, particularly the first CPU server.  To optimize the computational time for generic numerical simulations, various combinations of compiling flags, FORTRAN compilers, and parallelization strategies have been investigated. A database of results has been established, with a focus on pure neoclassical transport, following the achievement of the ideal configuration. We have been able to validate the current numerical codes through comparisons with analytical outcomes.

The objective of the validation of our proposed tokamak plasma perturbations’ inverted model against the JET experimental results regarding the radial localization of the modes has been fulfilled in an accurate and faster manner especially due to the use of our improved computing hardware achieved within the framework of this project. Also, objective of checking of the local safety factor profiles without relying on a consistent perturbations’ location the former is usually derived upon, has been accomplished. The significant computing power improvement this project has facilitated, have notably increased the computing speed, and eased the obtaining of our research results.

Consolidarea cercetărilor privind fuziunea nucleara în România SNFR-RO

Scopul proiectului este de a consolida participarea Romaniei la proiectul de cercetare EUROfusion prin modernizarea echipamentelor destinate acestor cercetari, dezvoltarea de infrastructura de cercetare dedicata si cresterea coeziunii echipelor de cercetatori. Atingerea acestui obiectiv va permite obtinerea unor progrese stiintifice semnificative in ceea ce privesc cercetarile desfasurate in cadrul pachetelor de lucru EUROfusion WPPWIE, WPMAT, WPPRD, WPMAG, WPBB, WPTE, WPSA.

In cadrul WPPWIE, unul din obiective a fost dezvoltarea unei proceduri pentru a produce probe tritiate cu nivele diferite de activitate si a unui montaj experimental pentru a monitoriza comportamentul de eliberare a tritiului din materiale relevante pentru fuziunea nucleara. Experimentele au fost realizate in colaborare dintre Departamentul de Plasma de Temperatura Joasa, INFLPR, responsabil pentru detectia cantitativa a eliberarii tritiului si Departamentul de Radioizotopi si Radiatie, IFIN-HH pentru tritierea probelor. De asemenea s-au s-au și analizat probe de wolfram depus pe  substrat de molibden prin tehnica HiPIMS. Aceste probe au fost expuse la tritiu, iar ulterior s-a monitorizat desorbția tritiului, analizată cu ajutorul spectroscopiei de desorbție termică (TDS). Înainte de măsurarea concretă a tritiului din probele de wolfram, s-a efectuat o calibrare pentru determinarea corectă a cantității de T, folosind deuteriu și hidrogen, deoarece calibrarea directă cu T2 nu este posibilă din motive de siguranță. După calibrare, s-a măsurat cantitatea de tritiu eliberată din probele analizate prin încălzire până la 1325 K. S-a observat că desorbția începe la temperaturi ridicate, de 450oC, iar profilul de desorbție este larg, cuprinzând diferite mecanisme de captare și eliberare a tritiului. Se remarcă un vârf principal la 550°C, urmat de un alt vârf de intensitate maximă la 700°C. Analizele sugerează că tritiul este absorbit prin suprafață, iar difuzia joacă un rol important în profilul de desorbție, tritiul fiind captat în situri energetice favorabile, cum ar fi vacanțele sau defectele din material.

Un alt obiectiv a fost de a produce acoperiri W-O utilizand tehnica de deupunere HiPIMS (High Power Magnetron Sputtering). Au fost obtinute straturi din sistemul wolfram-oxigen. Straturile obtinute au fost analizate prin XPS, XRD si GDOES. Compozitia chimica a straturilor a variat in domeniul 7.5-40 at.%. Sursa de putere pentru HiPIMS a fost achizitionata utiolizand fondurile alocate in cadrul acestui proiect. Acoperiri W-O Coatings cu grosimi de 1.3-3.2 µm si concentratie de oxygen intre 1.7 at.% si  8.5 at.% au fost produse si analizate.

Tot in perspectiva activitatilor viitoare din cadrul  WPPWIE, a fost proiectat, configurat și testat un sistem de detectie a speciilor W care pot fi eliberate in plasma in urma fenomenului de sublimare a oxizilor W. Acest sistem este util pentru obtinerea de detalii privind stabilitatea suprafetelor de W in raport cu expunerea la molecule oxidante (oxygen, vapori de apa) inerente ca impuritati sau prezente in Tokamak datorita contaminarilor accidentale. Sistemul configurat consta din asocierea unor surse de sublimare cu temperatura controlata cu metode de evaluare a procesului de sublimare, fie prin analiza chimica a depozitelor colectate  pe substraturi dedicate, fie prin detectia speciilor sublimate prin spectrometrie de masa.  Acest sistem este util pentru investigarea mobilizării și transportului prafului de W de pe suprafețe plasate în vid, sub acțiunea fluxurilor de gaze sau a campurilor electrice. De asemenea, a fost proiectată o cameră de vid si au fost achizitionate componentele pentru sistemul de pompare asociat, elemente constituiente ale unui echipament  dedicat experimentelor de sinteza in plasma în condiții controlate a nanoparticulelor de W, simultan cu diagnosticarea optica in-situ a transportului prafului sintetizat.

In cadrul activitatilo de cercetar din cadrul WPMAT au fost efetuate simulari numerice detaliate privind comportarea materialelor. Pachetul software Thermo-calc, dezvoltatepe baza CALPHAD, impreuna cu baze de date termodinamice adecvate poate fi utilizat pentru predictia evolutiei proprietatilor materialelor. Simularile descriu suficient de bine regimul de echilibru al fazelor pentru o marja larga de temperaturi. Astfel de simulari reduc numarul de experimente si consumul de materiale. Totusi, validarea experimentala nu poate fi complet eliminata. Aceste simulari au permis evaluarea utilitatii aplicarii acestei metodologii pentru alaiajele de tip HEA. CALPHAD a fost folosit pentru a investiga sistemul W-Ta-V-Fe-Ti, materialele cu bariere termice Cu-(Fe,Ta,Ti,W) și noi materiale CuCrFeV (Ti, Ta, W, Mo). Toate aceste materiale sunt, de asemenea, investigate experimental în cadrul activitatilor EUROfusion și, prin urmare, putem evalua acuratețea modelării CALPHAD față de rezultatele experimentale, precum și comparativ cu alte posibile abordări de modelare. O ruta de metalurgie a pulberilor a fost dezvoltată și utilizată pentru a produce aliaje Cux-CrFeVTi HEA care sunt investigate ca precursori pentru partea bogată în Cu a unui FGM W-Cu. Posibilitatea de a produce in INCDFM pulberi de tip HEA a fost de asemenea testata. Compozitia pudrelor a fost determinata prin simulari termodinamice.  Compozitele W-HEA au fost consolidate prin tehnici SPS si analizele au arata ca o mica concentratie de material pur W este pastrata. Facilitatea de iradiere cu electroni de la INFLPR a fost upgradata in vederea cresterii fluentei de electroni, ceea ce spoerste eficienta experimentelor.

Pentru sustinerea activitatilor din cadrul WPMAT, dar de importanta egala si pentru WPMAG, o atentie soeciala a fost acordata metodelor de imagistică cu raze X pentru evaluări complete ale integrității microstructurale și cartografierea compoziției în materiale, componente și procese relevante pentru fuziunea nucleară. Tehnicilor de investigare imagistică s-au imbunatatit prin implementarea microtomografiei combinate cu raze X cu energie dublă (DEXCT), fluorescenței cu raze X cu microfascicul (microXRF) și testare nedistructivă cu undă termică (TWNT). Aceste upgrade-uri sunt esențiale în creșterea preciziei și a capacităților metodologiilor noastre de imagistică. Proiectul a inclus achiziția unei camere FLIR și a unui laser pulsat pentru optimizarea metodelor de imagistică termică utilizate în TWNT. Aceste echipamente contribuie la dezvoltarea unor metode alternative de testare nedistructivă a componentelor dezvoltate în cadrul pachetelor de lucru WPMAG/WPENS (Test Cell Liner) și WPENR (benzi HTS).

In vederea realizarii activitatilor dedicate dezvoltarii HCPB breading blanket, programele de proiectare asistata 2D si 3D achizitionate, complementare celor existente, au imbunatatit capacitatea de modelare 2D si 3D in vederea proiectari si constructiei de standuri experimentale pentru caracterizarea de materiale necesare dezvoltarii sistemului de extractie si recuparare tritiu (TER) aferent DEMO HCPB. Aditional, utilizand add-on-ul PIE pentru CATIA, s-a dezvoltat modelul 3D pentru sistemul TER bazat pe rezultatele experimentale din programul de cercetare aferent sistemului.

Tot in cadrul WPBB un ansamblu experimental existent a fost imbunatatit cu senzori, pompe și fitinguri pentru a investiga formarea oxizilor pe probe de materiale relevante pentru constructia sistemului TER al HCPB, cum ar fi otelul inoxidabil și EUROFER 97. Investigatiile a avut ca obiectiv principal observarea formarii de oxid de crom pe probele supuse conditiilor relevante pentru sistemul de extractie și indepartare a tritiului in cadrul HCPB BB. Rezultatele arata ca pe ambele tipuri de probe (SS și EUROFER97) se formeaza oxizi de crom, dar in cantitate mai mica pe probele EUROFER. Pana in prezent, oxizii par a fi stabili, insa testele vor continua pe perioade mai lungi pentru a identifica evolutia stratului de oxid in timp.

O serie de imbunatatiri ale capacitatii de calcul (hardware si software) au fost implementate pentru a sprijini activitati de cercetare desfasurate in cadrul WPTE si WPSA. Acestea au permis ca sa se poata demonstra pe baza evaluarii variatie informationale sau prin utilizarea unor indicatori statistici pentru analiza seriilor temporale corespunzatoare semnalului de diagnostica  ce descrie echilibrul magnetic al plasmei poate fi un instrument efficient pentru identificarea disruptiilor in plasma.

O alta preocupare in cadrul WPTE se refera la ințelegerea și predicția transportului turbulent în dispozitivele tokamak. Acest lucru ar putea fi realizat într-un timp relativ redus folosind o bază de date de coeficienți de transport derivați pentru mulți parametri ai plasmei. Pentru finalizarea sarcinilor legate de participarea la WPTE s-au folosit noile capacitati hardware, in particular primul server CPU. Pentru a optimiza timpul de calcul pentru simulări numerice generice, au fost investigate diferite combinații de steaguri de compilare, compilatoare FORTRAN si strategii de paralelizare. S-a constituit o baza de date de rezultate, cu accent pe transportul neoclasic pur, in urma realizarii configuratiei ideale. Codurile numerice actuale ai fost validated prin comparații cu rezultatele analitice.

De asemenea, capacitatile sporite de calcul au fost estrem de utile pentru atingerea obicetivului privind verificarea profilurilor factorului de securitate in instalatiile tokamak fara a ne folosi de existenta unei locatii consistente a perturbatiilor din plasma pe baza caruia, indeobste, factorul de securitate e determinat. Imbunatatirea semnificativa a puterii de calcul facilitate de finantarea acestui proiect, a crescut in mod notabil viteza de calcul si a usurat obtinerea rezultatelor. Obiectivul validarii modelului inversat al perturbatiilor din plasma tokamak pe care l-am propus, in raport cu rezultatele experimentale de la JET privitoare la localizarea radiala a perturbatiilor, a fost indeplinit cu acuratete si rapiditate datorate cu precadere folosirii unui hardware de calcul imbunatatit, a carui achizitie a fost inlesnita de existenta proiectului de fata.

Papers

1. Y. Zayachuk, I. Jepu, M. Zlobinski, C. Porosnicu, N. Catarino, E. Pajuste, P. Petersson, L. Dittrich, J. P. Coad, E. Grigore, C. Postolache , E. Alves, G. Kizane, M. Rubel, A. Widdowson , Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of uncertainty and discrepancy sources, Nucl. Fusion, 63(9), DOI 10.1088/1741-4326/ace2d2.
2. S. Soni, S. Atikukke; M. Veis, N. Bolouki, P. Durina, P. Dvorák, M. Mrkvicková, E. Grigore, P. Veis, Depth profiling of W-Ta based fusion-relevant samples using picosecond laser ablation, Spectrochimica, Acta Part B: Atomic Spectroscopy, 216 (2024) 106930.
3. S Atikukke , M Veis , W Khan, E. Grigore, F. Baiasu, P. Ďurina, T. Roch, P. Dvořákb, P. Veis, Resonant Laser Induced Breakdown Spectroscopy for quantitative elemental depth profile analysis of WTa coating, Nuclear Materials and Energy, 38 (2024) 101558
4. S.D. Stoica, C. Craciun, T. Acsente, B. Mitu, G. Dinescu, Evidence for molecular tungsten ionic species presence in impurity-seeded hydrogen plasma in contact with W surfaces, Plasma Processes and Polymers (2024) e2300227; https://doi.org/10.1002/ppap.202300227
5. R. Martins, A.P. Gonçalves, J.B. Correia, A. Galatanu, E. Alves, M. Dias, Simulation and study of the milling parameters on CuFeTaTiW multicomponent alloy, Nuclear Materials and Energy 38 (2024) 101568, https://doi.org/10.1016/j.nme.2023.101568
6. R. Martins, A.P. Goncalves, J.B. Correia, A. Galatanu, E. Alves, E. Tejado, J.Y. Pastor, M. Dias, Simulation, Structural, Thermal and Mechanical Properties of the FeTiTaVW High Entropy Alloy, Metals 14 (2024) 00436, https://doi.org/10.3390/met14040436
7. A. Rodríguez-Lopez, B. Savoini, M.A. Monge, A. Galatanu, M. Galatanu, Evaluation of thermal properties of CuCrFeV (Ti, Ta, W, Mo) for nuclear fusion applications, Nuclear Materials and Energy 41 (2024) 101767, https://doi.org/10.1016/j.nme.2024.101767
8. M. Galatanu, W. Pantleon, M. Enculescu, M. Grigoroscuta, D. Ticos, A. Galatanu, Improved mechanical properties of Tungsten with dispersed nanometric ZrC particles processed by SPS  and a subsequent thermo-mechanical treatment, to be submitted to Metals by 10.12.2024
9. M. Galatanu, M. Enculescu, I. Assahsahi, A. Galatanu, Effects of Cr, V and refractory HEA dispersoids on thermophysical and mechanical properties of W matrix materials, to be submitted in the next 3 months
10. G. Ana, O. Balteanu, I. Cristescu, R. Ana, Concept for HCPB TER using non-evaporable getters for tritium recovery, Fusion Engineering and Design, 201 (2024) 2024
11. Zani, L., Babouche, R., Barabaschi, P., Cau, F., Davis, S., Di Pietro, E., H. Hurzlmeier, J. Lorenzo , A. Louzguiti , M. Lungu , N. Hajnal, M. Parody , A. Portone , I. Tiseanu , V. Tomarchio , F. Topin , M. Verrecchia, and M. Wanner, (2024). Extended Analysis of TF02 Feeder Performance and Risks During Operation in JT-60SA Tokamak. IEEE Transactions on Applied Superconductivity.
12. Mahmood, M. A., Diana, C., Sajjad, U., Mihai, S., Tiseanu, I.,Popescu, A. C. (2024). Printed layers height calibration curve and porosity in laser melting deposition of Ti6Al4V combining experiments, mathematical modelling and deep neural network, Rapid Prototyping Journal, 30(3), 415-429.
13. Babouche, R., Zani, L., Louzguiti, A., Turck, B., Duchateau, J. L., Topin, F., Tiseanu, I, Lungu, M.,  Dumitru, D. (2023). Inputs generation for COLISEUM coupling losses model using X-ray tomography: analytic and experimental approaches. Fusion Engineering and Design, 192, 113587.
14. L.M. Pomârjanschi, Neural networks for turbulent transport prediction in a simplified model of tokamak plasmas, Plasma Physics and Controlled Fusion 66 (6), 065007, 2024
15. R. Rossi, M. Gelfusa, T. Craciunescu, I. Wyss, J. Vega, A. Murari, A hybrid physics/data-driven logic to detect, classify, and predict anomalies and disruptions in tokamak plasmas, Nucl. Fusion 64 (2024) 046017

Conferences and Workshops

1. C. Craciun, G. Dinescu, S. D. Stoica, B. M. Mitu, T. Acsente, Identification of molecular tungsten ionic species in plasma by mass spectra fitting, poster presentation at the International Conference on Laser, Plasma and Radiation – Science and Technology; (ICLPR-ST) June 14-17, 2024 Danube Delta, Romania
2. T. Acsente, B. Mitu, V. Satulu, E. Matei, G. Dinescu, MSGA plasma jet cluster source: a new tool for nanomaterial synthesis, oral presentation at the  22^st International Balkan Workshop on Applied Physics (IBWAP 2024)  Constanţa, Romania, July 9-12, 2024 
3. A. Galatanu, Improved thermo-physical and mechanical properties of Tungsten with dispersed nanometric ZrC particles processed by SPS  and a subsequent thermo-mechanical treatment, M. Galatanu at ROCAM 2024, 10th International Edition, 15-18 July, Bucharest, Romania.
4. V. Corato, H. Bajas, R. Bonifetto, P. Bruzzone, N. Bykovskiy, G. Celentano, G. De Marzi, A. Masi, L. Muzzi, M. Ortino, K. Sedlak, I. Tiseanu, D. Uglietti, A. Zappatore, Progress in technological solutions for EU-DEMO magnets advanced conductors, Superconductivity & Particle Accelerators 2024, 21-24 Oct. Krakow, Poland.
5. I. Dinca, I. Tiseanu, I. Leu, L. Petculescu, G, Iacobeanu, A. Sima, C. Dobrea “Exploring the Past: Applications of X-Ray Techniques Investigations” 22nd International Balkan Workshop on Applied Physics and Materials Science Constanta, Romania, July 09-12, 2024; S4 P7 poster presentation
6. C. Dobrea, I. Tiseanu, A. SIma, I. DInca, A.-I. Leu “Mobile X-Ray Scanner for Large Size Samples Concept” 22nd International Balkan Workshop on Applied Physics and Materials Science Constanta, Romania, July 09-12, 2024; S5 P6 poster presentation
7. G. Miron et al., “Derivation of the q=1 dynamic profile from the 1/1 perturbation amplitude”, 50th EPS Plasma Conference, P1-087, Salamanca, Spain, 08-12.07.2024.
8. L. M. Pomarjanschi, D. I. Palade, Neural networks for turbulent transport prediction in a simplified model of tokamak plasmas, The International Conference on Laser, Plasma and Radiation – Science and Technology (ICLPR-ST), 16-21 Iunie, Danube Delta, Romania.
9. T Craciunescu, A, Murari, Time series derived indicators for fusion plasma disruption prediction, 33rd Symposium on Fusion Technology, 22-27 Sept., Dublin City University, Ireland.
10. T. Craciunescu, A. Murari, R. Rossi, M. Gelfusa, Time series analysis for fusion plasma disruption prediction studies, The International Conference on Laser, Plasma and Radiation – Science and Technology (ICLPR-ST), 16-21 Iunie, Danube Delta, Romania.
11. T. Craciunescu, A. Murari,  Concept-Drift Detection for Fusion Plasma Disruption Prediction, 17th Chaotic Modeling and Simulation International Conference Chania, Crete, Greece, 11 – 14 June, 2024.
12. R.  Rossi, A. Murari, T. Craciunescu, M. Gelfusa, A control-oriented approach to disruption prediction with a view on the reactor, The International Conference on Laser, Plasma and Radiation – Science and Technology (ICLPR-ST), 16-21 Iunie, Danube Delta, Romania.
13. Ye.O. Kazakov, M. Nocente, J. Garcia, J. Ongena, V.G. Kiptily, M. Baruzzo, D. Keeling, M. Maslov , C. Perez von Tun, Ž. Štancar, H. Weisen, A. Cardinali, C. Castaldo, A. Chomiczewska, R. Coelho, T. Craciunescu, E. Delabie, E. de la Luna, M. Dreval, R. Dumont, P. Dumortier, F. Durodie, A. Hakola, P. Jacquet, D. King, K. Kirov, M. Lennholm, E. Lerche, C. Lowry, M. Mantsinen, I. Monakhov, C. Noble, E. Panontin, S.D. Pinches, D. Rigamonti, M. Salewski, S. Sharapov, H. Sheikh, D. Van Eester, N. Wendler, Optimizing ion heating in D-T plasmas with three-ion ICRF scenarios: insights from JET and strategies for future tokamaks, 50th EPS Conference on Plasma Physics (EPS 2024), July 8-12, Salamanca, Spain.
14. M. Tardocchi , A. Dal Molin , G. Marcer , M. Rebai , D, Rigamonti , J. Scionti , M. Dalla Rosa , G. Gorini,, G. Grosso , A. Muraro , M. Nocente, E. Perelli-Cippo , M. Pillon , O. Putignano , M. Angelone , A. Bracco , F. Camera , Z. Ghani , V. Kiptily , Y. Kazakov , E. Panontin , T. Craciunescu , E. M. Khilkevitch , A. E. Shevelev, The new GETART method for measurement of the fusion power in DT magnetic confinement fusion based on absolute detection of 17 MeV gamma rays,  25th High Temperature Plasma Diagnostics Conference (HTPD 2024), 21-25 April, Asheville, North Carolina, USA.
15. Z. Ghani , P.J. Bonofiglo , T. Craciunescu , A. Dal Molin , J. Eriksson , M. Fitzgerald , V. Goloborodko , M.V. Iliasova , E.M. Khilkevitch , M. Nocente , S. Menmuir , M. Podestà , M. Poradzinski , D. Rigamonti , J. Rivero-Rodriguez, Z. Stancar, S.E. Sharapov , A.E. Shevelev , H. Sun , D.M. Taylor , M. Tardocchi , P. Beaumont , F. Belli, F.E. Cecil, C.D. Challis , R. Coelho , M. Curuia, R. Dumont, J. Garcia, M. Garcia-Munoz, J. Hobirk, P. Jacquet , E. Joffrin , A. Kappatou, Ye. Kazakov, D. Keeling , K. Lawson , I. Lengar , M. Lennholm , E. Lerche , C.F. Maggi , J. Mailloux , P. Mantica, M.J. Mantsinen, D. Marocco, M. Maslov , C. Perez von Thun, F. Rimini , P. Siren, D. Van Eester, “Observation of fusion-bone alpha particles in Joint European Torus”, Torino International Workshop on Fundamental Plasma Physics, Torino, 21-23 June, 2024.

Developed technologies

1. C. Porosnicu, A. Anghel, Procedure for calibrated T loading in W/Mo samples. In colaboration with IFIN-HH, INFLPRdeveloped a procedure (model) for obtaining samples with defined T content for future use in fusion related studies.
2. C. Porosnicu, B. Butoi, Procedure fot H isotope calibration in the TDS experimentIn our current work we developed a procedure to perform a calibration aimed at an accurate quantification of the T release from samples. The quantification of the total tritium release from the samples will be made by summing up the contributions corresponding to mass 5 (TH) and mass 6 represented by TT molecule.
3. A. Galatanu, A. Jianu, M. Galatanu (INCDFM), Powder metallurgy route to produce refractory HEAs based on mechanical alloying and spark plasma sisntering
4. A Galatanu, M. Cioca, A. Ighigeanu, M. Galatanu, FAST based technology to join refractory HEAs with W, including new design for graphite molds (2024)
5. M. Galatanu, A Galatanu, M. Cioca, A. Ighigeanu, FAST based technology to join Cu-based materials with HEAs at low temperatures (2024)

Experimental models, prototypes

1. System for the investigation of the W dust production mechanisms in fusion relevant plasma in contact with tungsten surfaces. The system is useful in fusion technology investigations, for establishing the Tokamak operation conditions leading to the smallest production of tungsten dust. It consists of a magnetron sputtering plasma source placed in a small chamber where the dust is synthesized from the sputtered atoms by aggregation in hydrogen plasmas mixed with gases used for divertor detachment (Ne, Ar, Kr). The particles are extracted from the small chamber and collected for characterization. The system can be used also for producing nanoparticles for nanotechnology applications (supercapacitors, sensors, catalytic devices).   (WPPWIE)
2. Experimental model for total tritium release determiantion (WPPWIE)
3. A new HEA-based FGM design including refractory type HEA containing Cu and W and 2 different Cu-based HEAs for which at least 2 other elements are also included in the first refractory HEA (2024) (WPMAT)
4. Experimental model to produce refractory HEAs based on mechanical alloying and spark plasma sintering (WPMAT)
5. Dual-Energy X-ray Computed Tomography (DEXCT) experimental model was developed (WPMAG)
6. Experimental model/ rig has been enhanced: An existing experimental rig (EuCOTES) has been enhanced with sensors, pumps and fittings in order to investigate the formation of oxides on samples of relevant materials for the construction of the HCPB TER system, like stainless steel and EUROFER 97. (WPBB)

Demonstrators

1. A multi-layer demonstrator including 1 layer pure W, 3 FGM layers (as designed abov) and a CuCrZr layer (2024) A. Galatanu, M. Galatanu, G. Ruiu (INCDFM)

OSIM patent applications

1. D. Avram, C. Tiseanu, I. Porosnicu “Metoda termografică cu rezoluție spațială și rezoluție de temperatură imbunătățite, bazată pe dinamica emisiei fosforilor”, Buletin Oficial de Proprietate Industriala, pag. 28.
2. Galatanu Andrei, Ighigeanu Adelina, Cioca Mihai, Popescu Bogdan; INCDFM, “Matrita de grafit cu geometrie variabila pentru egalizarea pierderilor de caldura radiata in timpul proceselor de lipire prin FAST”, 2024 in pregatire