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1

Numerical studies of plasma edge in W7-X with 3D FINDIF code

Jabłczyńska Małgorzata, Pełka Grzegorz, Jakubowski Marcin, Ślęczka Marcin

Nukleonika

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2023

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Vol. 68, No. 4

83--90

EN

Modelling of the plasma transport for inherently three-dimensional (3D) problems as in stellarators requires dedicated complex codes. FINDIF is a 3D multifl uid plasma edge transport code that has been previously successfully used for the analysis of energy transport in the TEXTOR-DED tokamak [1], where 3D perturbations led to an ergodic structure of fi eld lines in the plasma edge. The ongoing efforts to apply it meaningfully to Wendelstein 7-X (W7-X) plasma problems resulted in advancements in the main model and accompanying tools for mesh generation and post-processing. In order to verify the applicability of the code and to compare with the reported simulation (EMC3-EIRENE) and experimental (OP1.1) results, a series of simulations for varying plasma density, temperature and anomalous transport coeffi cients as well as for fi xed input power were performed. The connection length pattern of FINDIF traced magnetic fi eld lines on the limiter was reproduced and its impact on heat loads was confi rmed. An increase in the peak heat load on the limiter with a rise in plasma density, temperature and anomalous plasma transport coeffi cients was observed. The decay lengths of density, electron temperature and heat fl ux did not change with density, and were decreasing with temperature and increasing with anomalous plasma transport coeffi cient, which was compared to the simple scrape-off layer (SOL) model.

2

Progress in stellarator research at IPP-Kharkov

Moiseenko V. E., Lozin O. V., Shapoval A. M., Dreval M. B., Kulyk Y. S., Mironov Y. K., Romanov V. S., Pashnev V. K., Sorokovoy E. L., Petrushenya A. A., Ozherel’ev F. I., Kozulya M. M., Konovalov V. G., Maznichenko S. M., Garkusha I. E.

Nukleonika

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2016

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Vol. 61, No. 2

91--97

EN

A new antenna of ‘crankshaft’ type has been installed in the Uragan-2M device in order to increase the plasma density and heating below the ion cyclotron frequency. Antenna operation is modelled by 1D code, which solves boundary problem for time-harmonic Maxwell’s equations in radially non-uniform plasma cylinder. In recent experiments with this antenna, the SXR, CV, OV and OII emission measurements indicate that the light impurity radiation barrier is overcame at this device. Plasma with a temperature of ~50 eV exists during a short period of a few milliseconds. Then the radiation collapse comes owing to strong infl ux of impurities to the plasma column. A new magnetic diagnostics has been installed at Uragan-3M. Using it the poloidal magnetic fi eld is measured and the shift of toroidal current in major radius is registered. A miniature pinhole camera array for spatially and temporally resolved measurements of soft X-ray (SXR) plasma emission has been recently installed on the U-3M. Different shapes of the SXR emission profi le has been observed in different discharge conditions.

3

Nuclear fusion and its large potential for the future world energy supply

Ongena J.

Nukleonika

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2016

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Vol. 61, No. 4

425--432

EN

An overview of the energy problem in the world is presented. The colossal task of ‘decarbonizing’ the current energy system, with ~85% of the primary energy produced from fossil sources is discussed. There are at the moment only two options that can contribute to a solution: renewable energy (sun, wind, hydro, etc.) or nuclear fission. Their contributions, ~2% for sun and wind, ~6% for hydro and ~5% for fission, will need to be enormously increased in a relatively short time, to meet the targets set by policy makers. The possible role and large potential for fusion to contribute to a solution in the future as a safe, nearly inexhaustible and environmentally compatible energy source is discussed. The principles of magnetic and inertial confinement are outlined, and the two main options for magnetic confi nement, tokamak and stellarator, are explained. The status of magnetic fusion is summarized and the next steps in fusion research, ITER and DEMO, briefly presented.

4

Fusion 2050 : European and Polish Perspective

Romaniuk R. S.

International Journal of Electronics and Telecommunications

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2014

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Vol. 60, No. 1

95-101

EN

Fusion, in all its varieties, is a very current subject of science and technology. The results of strongly exothermic reaction of thermonuclear fusion between nuclei of deuterium and tritium are: helium nuclei and neutrons, plus considerable kinetic energy of neutrons of over 14 MeV. DT nuclides synthesis reaction is probably not the most favorable one for energy production, but is the most advanced technologically. More efficient would be possibly an aneutronic fusion. The EU by its EURATOM agenda prepared a Road Map for research and implementation of Fusion as a commercial method of thermonuclear energy generation in the time horizon of 2050. The milestones on this road are tokomak experiments JET, ITER and DEMO, and neutron experiment IFMIF. There is a hope, that by engagement of the national government, and all research and technical fusion and plasma communities, part of this Road Map may be realized in Poland. The infrastructure build for fusion experiments may be also used for material engineering research, chemistry, biomedical, associated with environment protection, power engineering, security, etc. Construction of such research and industrial accelerator and tokomak infrastructure may have potentially a profound meaning for the development of science and technology in Poland.

5

Fuzja : perspektywa 2050

Romaniuk R. S.

Elektronika : konstrukcje, technologie, zastosowania

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2013

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Vol. 54, nr 6

73-78

PL

W wyniku egzotermicznej reakcji fuzji termojądrowej jądra deuteru i trytu łączą się i powstaje jądro helu, neutron i wydzielana jest znaczna energia (kinetyczna neutronów 14 MeV). Reakcja nuklidów DT nie jest najkorzystniejsza z punktu widzenia produkcji energii, ale jest najbardziej zaawansowana techniczne. Korzystniejsze byłyby prawdopodobnie reakcje aneutronowe, Unia Europejska, poprzez swoją agendę EURATOM, opracowała mapę drogową mającą prowadzić do opanowania i wprowadzenia komercyjnej energetyki termojądrowej w perspektywie 2050. Kamieniami milowymi na tej drodze są eksperymenty tokamakowe JET, ITER oraz DEMO i eksperyment neutronowy IFMIF. Jest nadzieja, że przy zaangażowaniu rządu oraz wszystkich środowisk krajowych uczonych z dziedziny fuzji, część z tej mapy drogowej mogła by być realizowana w naszym kraju. Infrastruktura budowana dla eksperymentów fuzyjnych może być wykorzystywana także do badań materiałowych, chemicznych, biomedycznych, związanych z ochroną środowiska, energetyką, bezpieczeństwem, itp. Budowa takiej akceleratorowej infrastruktury badawczej i przemysłowej miałaby wielkie znaczenie dla rozwoju nauki i przemysłu atomistycznego w Polsce.

EN

The results of strongly exothermic reaction of thermonuclear fusion between nuclei of deuterium and tritium are: helium nuclei and neutrons, plus considerable kinetic energy of neutrons of over 14 MeV. DT nuclides synthesis reaction is probably not the most favorable one for energy production, but is the most advanced technologically. More efficient would be possibly aneutronic fusion. The EU by its EURATOM agenda prepared a Road Map for research and implementation of Fusion as a commercial method of thermonuclear energy generation in the time horizon of 2050. The milestones on this road are tokomak experiments JET, ITER and DEMO, and neutron experiment IFMIF. There is a hope, that by engagement of the national government, and all research and technical fusion communities, part of this Road Map may be realized in Poland. The infrastructure build for fusion experiments may be also used for material engineering research, chemistry, biomedical, associated with environment protection, power engineering, security, etc. Construction of such research and industrial accelerator infrastructure may have potentially a profound meaning for the development of science and technology in Poland.

6

Fizyka fotonu i badania plazmy : Wilga 2012

Romaniuk R. S.

Elektronika : konstrukcje, technologie, zastosowania

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2012

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Vol. 53, nr 9

170-176

PL

Artykuł jest trzecią częścią z kilku dokonującą przeglądu prac Jubileuszowego XXX Sympozjum Wilga 2012 Fotonika i Inż Fotonika i Inżynieria Internetu, dotyczącą fizyki fotonu i badań plazmy. Przedstawiono wybór prac prowadzonych przez młodych uczonych w różnych krajowych ośrodkach naukowych. Tematyka Sympozjum Wilga 2012 obejmowała: nanomateriały i nanotechnologie dla fotoniki, światłowody czujnikowe i nieliniowe, obiektowo zorientowane projektowanie sprzętu, metrologia fotoniczna, zastosowania optoelektroniki i fotoniki, łączne projektowanie fotoniki i elektroniki, systemy optoelektoniczne i fotoniczne dla astronomii, techniki kosmicznej i eksperymentów fizyki wysokich energii, systemy pomiarowe dla tokamaka JET, eksperyment Pi-of-the-sky, eksperymenty CMS i TOTEM. Sympozjum Wilga jest corocznym podsumowaniem rozwoju licznych prac doktorskich prowadzonych w tej tematyce w kraju.

EN

This paper is the third part (out of several) of the research survey of the Jubilee XXXth edition of WILGA Symposium on Photonics and Web Engineering, concerned with photon physics and plasma research. It presents a digest of chosen technical work results shown by young researchers from different technical universities from this country during the Jubilee XXXth SPIE-IEEE Wilga 2012 symposium on Photonics and Web Engineering. Topical tracks of the symposium embraced, among others, nanomaterials and nanotechnologies for photonics, sensory and nonlinear optical fibers, object oriented design of hardware, photonic metrology, optoelectronics and photonics applications, photonics-electronics co-design, optoelectronic and electronic systems for astronomy and high energy physics experiments, JET tokamak and pi-of-the sky experiments development.

7

Conceptual design of Light Impurity Monitor for Wendelstein 7-X

Książek I., Burhenn R., Musielok J.

Nukleonika

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2011

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Vol. 56, No. 2

155-160

EN

As plasma impurity ions can significantly influence the properties of a fusion plasma by dilution and enhancement of the radiation losses, the process of monitoring of their concentrations is one of the most important tasks. A Light Impurity Monitor is needed for monitoring the contamination of the stellarator plasma by carbon, nitrogen, boron, and oxygen impurities, which are indicators for the overload of the plasma facing components, leakage of the vacuum vessel, or wall condition, respectively. Their concentration will be estimated on the basis of emission intensities of their hydrogen-like ions. In this paper a conceptual design of such a spectrometer is presented, including the description of the geometry, the acquisition system and safety systems.