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1

Mathematical Calculation of Material Reliability Using Surface Roughness Feature Based on Plasma Material Interaction Experiment Results

Pahsa Alper, Aydoğdu Yıldırım, Göktaş Fahrettin

Eksploatacja i Niezawodność

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2023

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Vol. 25, no. 3

art. no. 169815

EN

The choice of reactor structural material design must take into account the TOKAMAK fusion reactors' structural reliability. Due to their high levels of heat and energy, fusion reactions have significant deformation effects, which reduce the efficiency of energy production in reactors. Material selection, erosion and damage, heat and stress management, reliability analysis, maintenance, and inspection are crucial elements in determining how reliable fusion reactors are. The focus of this work is on material selection and reliability analysis based on these parameters. The most common wall materials used in fusion reactors are tungsten, beryllium, steel, or graphite. It is advised to utilize aluminum because harmful Beryllium dust limits the study of this element. For this purpose, a target of aluminum samples is established with a plasma of He ions created by glow discharge. The dependability of the samples is determined by calculating the Weibull Distribution and measuring the roughness of the sample surfaces following exposure.

2

Optical roughness calculation for material structural analysis of energy structure applications under DC plasma processes

Pahsa Alper

Acta Innovations

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2023

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no. 49

39--48

EN

Surface qualities make aluminium a low-DC plasma interaction candidate. Aluminum for energy system structure building is studied experimentally, with observations obtained. Aluminum is cheap and frequently utilized in aerospace applications. The selection of materials for new applications of thermonuclear fusion energy, such as Tokamak reactor walls and fusion-based spaceship thrust structures, is important to decide in the design phase. In this study, an experimental setup application is created with low DC-type He plasma ions processed on aluminium pellet surfaces. The physical changes of the aluminium pellet material as an example of an energy structure surface are analysed under a scanned array microscope and 3D surface plots to detect optical roughness attributes.

3

Projekt ITER budowy eksperymentalnego reaktora jądrowego wytwarzającego energię w procesie kontrolowanej syntezy termojądrowej

Sosnowski Jacek

Inżynieria Elektryczna

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2021

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nr 6

18--19

4

Soft X-ray Diagnostic System Upgrades and Data Quality Monitoring Features for Tokamak Usage

Wojenski Andrzej, Linczuk Paweł, Piotr Kolasinski, Chernyshova Maryna, Mazon Didier, Kasprowicz Grzegorz, Pozniak Krzysztof T., Gaska Michał, Czarski Tomasz, Krawczyk Rafał

International Journal of Electronics and Telecommunications

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2021

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Vol. 67, No. 1

109--114

EN

The validation of the measurements quality after on-site diagnostic system installation is necessary in order to provide reliable data and output results. This topic is often neglected or not discussed in detail regarding measurement systems. In the paper recently installed system for soft X-ray measurements is described in introduction. The system is based on multichannel GEM detector and the data is collected and sent in special format to PC unit for further postprocessing. The unique feature of the system is the ability to compute final data based on raw data only. The raw data is selected upon algorithms by FPGA units. The FPGAs are connected to the analog frontend of the system and able to register all of the signals and collect the useful data. The interface used for data streaming is PCIe Gen2 x4 for each FPGA, therefore high throughput of the system is ensured. The paper then discusses the properties of the installation environment of the system and basic functionality mode. New features are described, both in theoretical and practical approach. New modes correspond to the data quality monitoring features implemented for the system, that provide extra information to the postprocessing stage and final algorithms. In the article is described also additional mode to perform hardware simulation of signals in a tokamak-like environment using FPGAs. The summary describes the implemented features of the data quality monitoring features and additional modes of the system.

5

Modelowanie i implementacja układu sekwencera sygnałów ładunkowych z detektora GEM dla szybkiego systemu diagnostyki gorącej plazmy tokamakowej

Kolasiński P., Późniak K., Czarski T., Chernyshova M., Gąska M., Linczuk P., Kasprowicz G., Krawczyk R., Wojeński A., Zabołotny W.

Przegląd Telekomunikacyjny + Wiadomości Telekomunikacyjne

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2018

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nr 4

86--91

PL

Przedstawiono autorską koncepcję architektury sekwencjonowania danych pomiarowych o dużej częstości, odbieranych z wielokanałowych układów detekcyjnych w czasie rzeczywistym. Na wstępie omówiono genezę pracy w odniesieniu do rozwoju rozwiązań systemów pomiarowych z równoległym przetwarzaniem danych. Wskazano na najważniejsze korzyści wynikające z zastosowania układu sekwencera. Przeprowadzono dyskusję proponowanej architektury oraz omówiono realizację modelu w języku Matlab w celu doboru parametrów użytkowych implementowanych rozwiązań. Przedstawiono implementację architektury układu sekwencera w systemie diagnostyki gorącej plazmy w tokamaku WEST.

EN

This paper describes developed architecture of the sequencer dedicated for high rate measurement data collected from multiple channels in real time. Introduction presents a brief description and genesis of the project and its achievements in relation to presently existing and used measurements system where parallel data processing is crucial. Authors point out advantages of the developed architecture. Additionally is discussed model of the architecture realized in MATLAB environment in order to select most optimal parameters adjusted to specific processes. Last sections presents implementation of the sequencer architecture in plasma diagnostics measurement system for WEST tokamak.

6

Thermal-hydraulic analysis of LTS cables for the DEMO TF coil using simplifi ed models

Lewandowska M., Dembkowska A.

Nukleonika

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2017

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Vol. 62, No. 1

23--28

EN

The conceptual design activities for the DEMOnstration reactor (DEMO) – the prototype fusion power plant – are conducted in Europe by the EUROfusion Consortium. In 2015, three design concepts of the DEMO toroidal field (TF) coil were proposed by Swiss Plasma Center (EPFL-SPC, PSI Villigen), Italian National Agency for New Technologies (ENEA Frascati), and Atomic Energy and Alternative Energies Commission (CEA Cadarache). The proposed conductor designs were subjected to complete mechanical, electromagnetic, and thermal-hydraulic analyses. The present study is focused on the thermal-hydraulic analysis of the candidate conductor designs using simplifi ed models. It includes (a) hydraulic analysis, (b) heat removal analysis, and (c) assessment of the maximum temperature and the maximum pressure in each conductor during quench. The performed analysis, aimed at verification whether the proposed design concepts fulfil the established acceptance criteria, provides the information for further improvements of the coil and conductors design.

7

COREDIV modelling of JET ILW discharges with different impurity seeding: nitrogen, neon, argon and krypton

Ivanova-Stanik I., Zagórski R.

Nukleonika

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2017

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Vol. 62, No. 1

3--7

EN

Numerical simulations with the COREDIV code of JET H-mode discharges with 25 MW of auxiliary heating in the ITER-like wall (ILW) configuration with different impurity seedings – nitrogen (N), neon (Ne), argon (Ar) and krypton (Kr) – are presented. All simulations have been performed with the same transport model and input discharge parameters like auxiliary heating, volume average plasma density, confi nement factor. Only the seeded impurity puff rate was changed in the calculations. It appears that for the considered heating power of 25 MW and relatively low volume electron average density = 6.2 × 1019 m–3, impurity seeding is necessary. It has been found that for every gas at the maximum level of the seeding rate, allowed by the code convergence, the power to the plate is reduced up to 2–4 MW, with electron temperature at the plate of about 2 eV, indicating semi-detached conditions in the divertor region. It should be noted, however, that in cases with low and medium Z impurity (N, Ne and Ar), tungsten radiation is a signifi cant part of radiation losses and stays above 22–32% of the total energy losses, but for high Z impurity (Kr) it is reduced up to 10% of the total losses. The maximum of the Kr radiation is between the pedestal region and separatrix, showing that radiative mantle can be created, which might have a strong influence on the plasma parameters in the pedestal region.

8

Szybki, niskolatencyjny system szeregowania danych pomiarowych implementowany w układzie FPGA

Kolasiński P., Poźniak K., Chernyshova M., Czarski T., Gąska M., Linczuk P., Kasprowicz G., Krawczyk R., Wojeński A., Zabołotny W.

Elektronika : konstrukcje, technologie, zastosowania

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2017

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Vol. 58, nr 8

40--45

PL

W artykule przedstawiono opracowane przez Zespół Autorów systemy szeregowania danych przychodzących z wielu źródeł w czasie rzeczywistym. Na wstępie krótko omówiono zasadę działania detektorów GEM wykorzystywanych do rejestracji promieniowania w tokamakach. Przedstawiono ogólnie budowę systemu do realizacji diagnostyki gorącej plazmy, działającego z dużą liczbą kanałów wejściowych. Szczegółowo omówiono system szeregowania danych. Przedstawiono wymagania algorytmu, opracowane koncepcje, napotkane problemy oraz implementacje algorytmów w układach FPGA. Dodatkowo przedstawiono przykładowe wyniki z działania systemu.

EN

This paper presents designed by the Research Team high performance sorting algorithms working in real time, for data coming from many concurrent sources. The introduction is a brief description of the basics of the GEM detectors, used for tokamaks’ radiation registration. In the paper is discussed the general design structure of electronic systems working with high number of input channels. In the article is described fast data processing, with focus on algorithms implemented in FPGA. Description covers in detail aspects of sorting algorithm. The article presents requirements of the algorithm, concepts, problems and implementation in the FPGA. The measurement result of the systems are also briefly discussed.

9

System zabezpieczeń elektronicznego systemu pomiarowego do diagnostyki gorącej plazmy tokamakowej

Gąska M., Kasprowicz G., Wojeński A., Chernyshova M., Czarski T., Kolasiński P., Jarosiński J., Krawczyk R., Linczuk P., Poźniak K., Zabołotny W.

Elektronika : konstrukcje, technologie, zastosowania

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2017

|

Vol. 58, nr 8

36--39

PL

W artykule przedstawiono opracowany przez Zespół Autorów system zabezpieczeń i diagnostyki dla detektora gazowego GEM. Na wstępie krótko omówiono zagrożenia na jakie narażony jest detektor GEM oraz elektroniczne systemy pomiarowe pracujące w bliskiej odległości od reaktora termojądrowego. Przedstawiono koncepcje modułu do ciągłego monitorowania stanu systemu do diagnostyki gorącej plazm. Pod względem bezpieczeństwa omówiono dwa kluczowe podsystemy: moduł zabezpieczeń i system chłodzenia cieczą. Opisano funkcjonalność systemu, przyjęte rozwiązania sprzętowe oraz implementacją oprogramowania. Na końcu przedstawiono praktyczne wykorzystanie systemu.

EN

This paper presents designed by the Research Team electronic protection and diagnostic system for GEM detectors. The introduction is a brief description of the hazards to which GEM detector and electronic measurement system operating close to fusion reactor are exposed. The concept of an electronic module for continuous monitoring of the state of the system for plasma hot plasma is presented. Two main safety subsystem are described: security module and liquid cooling system. Description cover aspects of system functionality, hardware construction and implemented firmware. Finally, the practical use of the system is presented.

10

Conceptual analysis of a thermonuclear power station with the tokamak type reactor

Pajączek Krzysztof

Archiwum Instytutu Techniki Cieplnej

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2017

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Vol. 3

31--52

EN

This paper concerns a technology of nuclear fusion reactors with magnetic containment of plasma in a tokamak and about using it in production of electricity. The reaction of the thermonuclear fusion is occurring in very high temperatures of the order of hundreds of millions degrees Kelvin. Such reactions are occurring in stars and produce the considerable quantities of energy. The closest natural fusion reactor is the sun in our Solar System. A power station based on a fusion reactor seems to be within reach of current technologies, however requires considerable efforts and the cooperation of many nations. Elements from which the thermonuclear power station will be built will have to be of high quality and of the precise execution. Thermonuclear reactor will consist of many parts which must be made appropriately and have a significant resistance to thermal fluxes and the neutron radiation. The analysis presented in this work regards production of electricity with applying the thermonuclear fusion. Most important system and elements that make up the tokamak type thermonuclear reactor are characterized. A few blends of fuel are considered for "burning" in the reactor, and most probable for the application is a blend of deuterium and tritium. A subject of the production of the tritium in cooling jackets with liquid lithium is brought up. Power station under consideration has a turbine cycle with steam as the working fluid. High-temperature plasma is the source of heat driving the power plant and the heat is being collected from the blanket of the reactor which surrounds plasma. Calculations were performed for the conceptual power station in three technological variants (different parameters of fresh and reheated steam). Matter of using the product after the thermonuclear reaction is raised. A review of a state-of-the-art technologies allows to conclude that the ITER is an important first step in thermonuclear fusion. Technology is available, clean, environment friendly and it would be very effective. Building fusion power plants requires outstanding technical capabilities, commitment and vision.

PL

W pracy zebrano informacje na temat technologii reaktorów fuzyjnych z magnetycznym utrzymaniem plazmy (typu tokamak) oraz o ich wykorzystaniu w produkcji energii elektrycznej. Reakcja fuzji jądrowej zachodzi w bardzo wysokich temperaturach rzędu setek milionów kelwinów, stąd też częste określenie fuzja termojądrowa. Reakcje takie zachodzą w gwiazdach i produkują znaczne ilości energii, najbliższy naturalny reaktor fuzyjny to Słońce znajdujące się w naszym układzie słonecznym. Elektrownia bazująca na reaktorze fuzyjnym jest w zasięgu aktualnych technologii, jednakże wymaga sporych starań oraz współpracy wielu narodów. Elementy, z których zostanie zbudowana elektrownia termojądrowa będą musiały być bardzo wysokiej jakości oraz bardzo precyzyjnie wykonane. Sam reaktor fuzji termojądrowej będzie składał się z wielu części, które muszą być odpowiednio wykonane oraz posiadać znaczną odporność na obciążenia cieplne czy promieniowanie neutronowe. Niniejsza praca dotyczy produkcji energii elektrycznej z zastosowaniem fuzji termojądrowej. Przedstawiono opis ważniejszych części wspomnianej elektrowni. Rozpatrywanych było kilka mieszanek paliwa do „spalenia” w reaktorze, przy czym najbardziej prawdopodobnym do zastosowania paliwem będzie mieszanka deuteru i trytu. Poruszony został również temat produkcji trytu w płaszczach chłodzonych płynnym litem. Rozważana elektrownia termojadrowa posiada obieg turbinowy z parą wodną jako czynnikiem roboczym. Źródłem ciepła jest wysokotemperaturowa plazma, a ciepło odbierane jest z płaszcza reaktora otaczającego tą plazmę. Wykonane zostały obliczenia dla koncepcyjnej elektrowni w trzech wariantach technologicznych (różne parametry pary świeżej i wtórnie przegrzanej) oraz poruszono sprawę wykorzystania produktu po reakcji termojądrowej. Przeprowadzona analiza studialno-obliczeniowa pozwala wnioskować miedzy innymi, że projekt ITER jest istotnym pierwszym krokiem na drodze ku fuzji termojądrowej. Technologia termojądrowa wydaje się być osiągalna, czysta i przyjazna dla środowiska, a co więcej bardzo efektywna. Budowa elektrowni opartej na fuzji jądrowej wymaga jednak wybitnych zdolności technicznych, obowiązkowości oraz nieco wizjonerskiego podejścia.

11

Optimization of soft X-ray tomography on the COMPASS tokamak

Imríšek M., Mlynář J., Löffelmann V., Weinzettl V., Odstrčil T., Odstrčil M., Tomeš M.

Nukleonika

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2016

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Vol. 61, No. 4

403--408

EN

The COMPASS tokamak is equipped with the soft X-ray (SXR) diagnostic system based on silicon photodiode arrays shielded by a thin beryllium foil. The diagnostic is composed of two pinhole cameras having 35 channels each and one vertical pinhole camera with 20 channels, which was installed recently to improve tomographic inversions. Lines of sight of the SXR detectors cover almost complete poloidal cross section of the COMPASS vessel with a spatial resolution of 1–2 cm and temporal resolution of about 3 s. Local emissivity is reconstructed via Tikhonov regularization constrained by minimum Fisher information that provides reliable and robust solution despite limited number of projections and ill-conditionality of this task. Improved border conditions and numerical differentiation matrices suppressing artifacts in reconstructed radiation were implemented in the code. Furthermore, a fast algorithm eliminating iterative processes was developed, and it is foreseen to be tested in real-time plasma control.

12

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

Ongena J.

Nukleonika

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2016

|

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.

13

Modelling of the soft X-ray tungsten spectra expected to be registered by GEM detection system for WEST

Syrocki Ł., Szymańska E., Słabkowska K., Polasik M., Pestka G.

Nukleonika

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2016

|

Vol. 61, No. 4

433--436

EN

In the future International Thermonuclear Experimental Reactor (ITER), the interaction between the plasma and the tungsten chosen as the plasma-facing wall material imposes that the hot central plasma loses energy by X-ray emission from tungsten ions. On the other hand, the registered X-ray spectra provide alternative diagnostics of the plasma itself. Highly ionized tungsten emits extremely complex X-ray spectra that can be understood only after exhaustive theoretical studies. The detailed analyses will be useful for proper interpretation of soft X-ray plasma radiation expected to be registered on ITER-like machines, that is, Tungsten (W) Environment in Steady-state Tokamak (WEST). The simulations of the soft X-ray spectra structures for tungsten ions have been performed using the flexible atomic code (FAC) package within the framework of collisional-radiative (CR) model approach for electron temperatures and densities relevant to WEST tokamak.

14

Energy composition of high-energy neutral beams on the COMPASS tokamak

Mitosinkova A., Stöckel J., Varju J., Weinzettl V.

Nukleonika

|

2016

|

Vol. 61, No. 4

419--423

EN

The COMPASS tokamak is equipped with two identical neutral beam injectors (NBI) for additional plasma heating. They provide a beam of deuterium atoms with a power of up to ~(2 × 300) kW. We show that the neutral beam is not monoenergetic but contains several energy components. An accurate knowledge of the neutral beam power in each individual energy component is essential for a detailed description of the beam- -plasma interaction and better understanding of the NBI heating processes in the COMPASS tokamak. This paper describes the determination of individual energy components in the neutral beam from intensities of the Doppler-shifted Dα lines, which are measured by a high-resolution spectrometer viewing the neutral beam-line at the exit of NBI. Furthermore, the divergence of beamlets escaping single aperture of the last accelerating grid is deduced from the width of the Doppler-shifted lines. Recently, one of the NBI systems was modifi ed by the removal of the Faraday copper shield from the ion source. The comparison of the beam composition and the beamlet divergence before and after this modifi cation is also presented.

15

Elektroniczne systemy pomiarowe do diagnostyki gorącej plazmy tokamakowej

Poźniak K., Byszuk A., Chernyshova M., Czarski T., Kasprowicz G., Kolasiński P., Krawczyk R., Linczuk M., Romaniuk R., Wojeński A., Zienkiewicz P., Zabłotny W.

Elektronika : konstrukcje, technologie, zastosowania

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2016

|

Vol. 57, nr 2

3--9

PL

W artykule przedstawiono opracowane przez Zespół Autorów wydajne elektroniczne systemy pomiarowe do diagnostyki gorącej plazmy tokamakowej bazujące na detektorach GEM. Na wstępie krótko omówiono realizowane eksperymenty fizyczne związane z gorącą plazmą oraz zasadę działania detektorów GEM, wykorzystywanych do rejestracji promieniowania miękkiego typu X emitowanego w tokamakach. Przedstawiono ogólną koncepcję budowy systemów elektronicznych do realizacji diagnostyki gorącej plazmy, działających z dużą ilość kanałów wejściowych oraz krótkim czasem przetwarzania danych. Omówiono dwa kluczowe systemy opracowywane przez Zespół: system sprzętowego histogramowania miękkiego promieniowania X oraz system szybkiej akwizycji potokowej miękkiego promieniowania X. Opisano budowę sprzętową systemów, opracowane koncepcje oraz implementacje oprogramowania (firmware oraz software) wraz z niezbędnymi algorytmami. Przedstawiono ponadto wyniki z działania systemów.

EN

This paper presents designed by the Research Team high performance electronic measurement system for hot tokamak plasma diagnostics, based on GEM detectors. The introduction is a brief description of the experiments related with hot plasma and the basics of the GEM detectors, used for tokamaks’ soft X-ray radiation registration. In the text is discussed the general design structure of electronic systems, working with high number of input channels and fast data processing. Two systems, designed by the Research Team, are also introduced: hardware soft X-ray histogramming system and fast serial soft X-ray data acquisition system. Description covers aspects of hardware construction, implemented firmware and software along with the necessary algorithms. The measurement result of the systems are also briefly discussed.

16

Selected methods of electronand ion-diagnostics in tokamak scrape-off-layer

Sadowski M. J.

Nukleonika

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2015

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Vol. 60, No. 2

199--206

EN

This invited paper considers reasons why exact measurements of fast electron and ion losses in tokamaks, and particularly i n a scrape-off-layer and near a divertor region, are necessary in order to master nuclear fusion energy production. Attention is also paid to direct measurements of escaping fusion products from D-D and D-T reactions, and in particular of fast alphas which might be used for plasma heating. The second part describes the generation of so-called runaway and ripple-born electrons which might induce high energy losses and cause severe damages of internal walls in fusion facilities. Advantages and disadvantages of different diagnostic methods applied for studies of such fast electrons are discussed. Particular attention is paid to development of a direct measuring technique based on the Cherenkov effect which might be induced by fast electrons in appropriate radiators. There are presented various versions of Cherenkov-type probes which have been developed by the NCBJ team and applied in different tokamak experiments. The third part is devoted to direct measurements of fast ions (including those produced by the nuclear fusion reactions) which can escape from a high-temperature plasma region. Investigation of fast fusion-produced protons from tokamak discharges is reported. New ion probes, which were developed by the NCBJ team, are also presented. For the fi rst time there is given a detailed description of an ion pinhole camera, which enables irradiation of several nuclear track detectors during a single tokamak discharge, and a miniature Thomson-type mass-spectrometer, which can be used for ion measurements at plasma borders.

17

Important problems of future thermonuclear reactors

Sadowski M. J.

Nukleonika

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2015

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Vol. 60, No. 2

331--338

EN

This paper concerns important and difficult problems connected with a design and construction of thermonuclear reactors, which have to use nuclear fusion reactions of heavy isotopes of hydrogen, i.e., deuterium (D) and tritium (T). There are described conditions in which such reactions can occur, and different methods of a high-temperature plasma generation, i.e., high-current electrical discharges, intense microwave pulses, and injection of energetic neutral atoms (NBI). There are also presented experimental facilities which can contain hot plasma for an appropriate period, and particularly so-called tokamaks. The second part presents the technical problems which must be solved in order to build a thermonuclear reactor, that might be used for energetic purposes. There are considered problems connected with a choice of constructional materials for a vacuum chamber, its internal parts, external windings generating a magnetic fi eld, and necessary shields. The next part considers the handling of radioactive tritium; the using of alpha particles (4He) for additional heating of plasma; recuperation of hydrogen isotopes absorbed in the tokamak internal parts, and a removal of a helium excess. There is presented a scheme of a future thermonuclear power plant and critical comments on a road map which should enable the construction of an industrial thermonuclear reactor (DEMO).

18

First dedicated observations of runaway electrons in the COMPASS tokama

Vlainić M., Mlynář J., Weinzettl V., Papřok R., Imríšek M., Ficker O., Vondráček P., Havlíček J.

Nukleonika

|

2015

|

Vol. 60, No. 2

249--255

EN

Runaway electrons present an important part of the present efforts in nuclear fusion research with respect to the potential damage of the in-vessel components. The COMPASS tokamak a suitable tool for the studies of runaway electrons, due to its relatively low vacuum safety constraints, high experimental flexibility and the possibility of reaching the H-mode D-shaped plasmas. In this work, results from the first experimental COMPASS campaign dedicated to runaway electrons are presented and discussed in preliminary way. In particular, the first observation of synchrotron radiation and rather interesting raw magnetic data are shown.

19

Synteza termojądrowa : przyszłość energetyki

Scholz M., Karpiński L., Woźnicka U.

Automatyka, Elektryka, Zakłócenia

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2015

|

Vol. 6, Nr 4(22)

110-116

PL

W artykule przedstawiono rolę, jaką może odegrać w produkcji energii synteza termojądrowa. Opisano zjawisko syntezy termojądrowej oraz pokazano w jaki sposób można ją przeprowadzić w warunkach ziemskich na urządzeniu tokamak. Omówiono stan i perspektywy rozwoju reaktorów termojądrowych opartych na układach typu tokamak. W podsumowaniu wymieniono najważniejsze wady i zalety tego sposobu produkcji energii.

EN

The future of thermonuclear fusion in global energy production is presented in the paper. The phenomena of fusion is described and it is shown how the fusion can be conducted on tokamak devices. The state and prospects of development of the fusion reactor based on the tokamak-type systems are presented. In summary, major advantages and disadvantages of this method of energy production has been discussed.

20

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.