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Autore: Grafiati

Pubblicato: 8 giugno 2024

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1

Betti, R., P. Y. Chang, B. K. Spears, K. S. Anderson, J. Edwards, M. Fatenejad, J. D. Lindl, R. L. McCrory, R. Nora e D. Shvarts. "Thermonuclear ignition in inertial confinement fusion and comparison with magnetic confinement". Physics of Plasmas 17, n. 5 (maggio 2010): 058102. http://dx.doi.org/10.1063/1.3380857.

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2

Keen, B. E., e M. L. Watkins. "Present State of Nuclear Fusion Research and Prospects for the Future". Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 207, n. 4 (novembre 1993): 269–78. http://dx.doi.org/10.1243/pime_proc_1993_207_049_02.

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This paper traces the development of nuclear fusion research and describes the basic principles involved. The most advanced device used to achieve controlled thermonuclear fusion is the magnetic confinement approach, utilizing the tokamak concept. The Joint European Torus (JET) is the largest tokamak in operation. The operating conditions are described and critical issues outlined. With concerted effort and international collaboration the possibility exists to produce a demonstration reactor.

3

Winterberg, F. "Coriolis force-assisted inertial confinement fusion". Laser and Particle Beams 37, n. 01 (marzo 2019): 55–60. http://dx.doi.org/10.1017/s0263034619000181.

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AbstractA fundamental problem for the realization of laser fusion through the implosion of a spherical target is Kidder's E−1/6 law, where E is the energy needed for ignition, proportional to the 6th power of the ratio R/R0, where R0 and R are the initial and final implosion radii, respectively. This law implies that the ignition energy is very sensitive to the ratio R0/R, or vice versa, the ratio R0/R is very insensitive to the energy input, with R0/R limited by the Rayleigh–Taylor instability. According to still classified data of the Centurion–Halite experiment at the Nevada Test Site, ignition would require an energy of ${\rm E}\simeq 50\,{\rm MJ}$, 25 times larger than the 2 MJ laser at the National Ignition Facility (NIF) reported in the New York Times. This means that even a tenfold increase from 2 to 20 MJ would only decrease the R/R0 ratio by an insignificant factor of 10−1/6 ≃ 0.7. To overcome this problem, it is proposed that the spherical target is replaced with a hollowed-out, rapidly rotating, cm-size ferromagnetic target, accelerated by a rotating traveling magnetic wave to a rotational velocity of ~1 km/s, at the limit of its tensile strength. In a rotating reference system, the general theory of relativity predicts the occurrence of negative gravitational field masses in the center of rotation, with their source located in the Coriolis force field. The density of this negative gravitational field mass can be larger than the magnitude of the positive mass density of a neutron star. The repulsive gravitational force causes the centrifugal force. For a magnetized plasma placed in the rapidly spinning, hollowed-out target chamber, this repulsive force can be balanced by the magnetic force generated by thermomagnetic currents of the Nernst effect. Such a configuration does not suffer from the Rayleigh–Taylor instability, but becomes a small magnetohydrodynamic generator, amplifying the magnetic field to values about equal to those of the Nernst effect, axially confining the plasma. By placing the spinning target in the center of a lithium vortex, the fusion neutrons absorbed in the vortex can breed tritium, and at the same time remove heat from the target chamber to sustain the Nernst effect. A hot spot is thereby produced in the target chamber, which launches a thermonuclear burn wave into a cylindrical deuterium–tritium configuration. With the stability of a rapidly rotating target greatly increased, and the range of 10 MeV electrons in the wall of the cm-size ferromagnetic target, an intense 10 MeV relativistic electron beam drawn from a 10 MJ Marx generator should be sufficient to implode the target for thermonuclear ignition.

4

Соболев, Д. И., e Г. Г. Денисов. "Волноводная антенна с расширенным угловым диапазоном для дистанционного управления направлением волнового пучка". Письма в журнал технической физики 44, n. 5 (2018): 69. http://dx.doi.org/10.21883/pjtf.2018.05.45710.16391.

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AbstractA new method for increasing the angular range of a waveguide antenna for remote steering of the wave-beam direction in thermonuclear-fusion experimental setups with plasma magnetic confinement is proposed. Characteristics for large beam inclination angles can be improved using the synthesized nonuniform waveguide profile. For small angles, the characteristics remain invariable, the waveguide profile differs only slightly from the regular shape, and can be fit to limited waveguide-channel sizes.

5

SCHWENN, ULRICH, W. ANTHONY COOPER, GUO Y. FU, RALF GRUBER, SILVIO MERAZZI e DAVID V. ANDERSON. "Three-Dimensional Ideal Magnetohydrodynamic Stability on Parallel Machines". International Journal of Modern Physics C 02, n. 01 (marzo 1991): 143–57. http://dx.doi.org/10.1142/s0129183191000147.

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On the path towards a thermonuclear fusion reactor there are several technological and physical uncertainties to be understood and solved. One of the most fundamental problems is the appearance of many sorts of instabilities which can either enhance the energy outflow or even destroy the magnetic confinement of the fusion plasma. The knowledge of such instabilities is a prerequisite to a good understanding of the behaviour of actual experiments, and to the design of new devices. Most of the effort is devoted to the study of axisymmetric toroidal configurations such as tokamaks or spheromaks and to helically twisted toroidal devices such as stellarators.

6

Schlossberg, D. J., A. S. Moore, J. S. Kallman, M. Lowry, M. J. Eckart, E. P. Hartouni, T. J. Hilsabeck, S. M. Kerr e J. D. Kilkenny. "Design of a multi-detector, single line-of-sight, time-of-flight system to measure time-resolved neutron energy spectra". Review of Scientific Instruments 93, n. 11 (1 novembre 2022): 113528. http://dx.doi.org/10.1063/5.0101874.

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In the dynamic environment of burning, thermonuclear deuterium–tritium plasmas, diagnosing the time-resolved neutron energy spectrum is of critical importance. Strategies exist for this diagnosis in magnetic confinement fusion plasmas, which presently have a lifetime of ∼1012 longer than inertial confinement fusion (ICF) plasmas. Here, we present a novel concept for a simple, precise, and scale-able diagnostic to measure time-resolved neutron spectra in ICF plasmas. The concept leverages general tomographic reconstruction techniques adapted to time-of-flight parameter space, and then employs an updated Monte Carlo algorithm and National Ignition Facility-relevant constraints to reconstruct the time-evolving neutron energy spectrum. Reconstructed spectra of the primary 14.028 MeV nDT peak are in good agreement with the exact synthetic spectra. The technique is also used to reconstruct the time-evolving downscattered spectrum, although the present implementation shows significantly more error.

7

Clery, Daniel. "Alternatives to tokamaks: a faster-better-cheaper route to fusion energy?" Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, n. 2141 (4 febbraio 2019): 20170431. http://dx.doi.org/10.1098/rsta.2017.0431.

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The use of thermonuclear fusion as a source for energy generation has been a goal of plasma physics for more than six decades. Its advantages are many: easy access to fuel and virtually unlimited supply; no production of greenhouse gases; and little radioactive waste produced. But heating fuel to the high temperature necessary for fusion—at least 100 million degrees Celsius—and containing it at that level has proved to be a difficult challenge. The ring-shaped magnetic confinement of tokamaks, which emerged in the 1960s, was quickly identified as the most promising approach and remains so today although a practical commercial reactor remains decades away. While tokamaks have rightly won most fusion research funding, other approaches have also been pursued at a lower level. Some, such as inertial confinement fusion, have emerged from nuclear weapons programs and others from academic efforts. A few have been spun out into start-up companies funded by venture capital and wealthy individuals. Although alternative approaches are less well studied, their proponents argue that they could provide a smaller, cheaper, and faster route to fusion energy production. This article will survey some of the current efforts and where they stand. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.

8

Abarzhi, S. I., e K. R. Sreenivasan. "Turbulent mixing and beyond". Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 368, n. 1916 (13 aprile 2010): 1539–46. http://dx.doi.org/10.1098/rsta.2010.0021.

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Turbulence is a supermixer. Turbulent mixing has immense consequences for physical phenomena spanning astrophysical to atomistic scales under both high- and low-energy-density conditions. It influences thermonuclear fusion in inertial and magnetic confinement systems; governs dynamics of supernovae, accretion disks and explosions; dominates stellar convection, planetary interiors and mantle-lithosphere tectonics; affects premixed and non-premixed combustion; controls standard turbulent flows (wall-bounded and free—subsonic, supersonic as well as hypersonic); as well as atmospheric and oceanic phenomena (which themselves have important effects on climate). In most of these circumstances, the mixing phenomena are driven by non-equilibrium dynamics. While each article in this collection dwells on a specific problem, the purpose here is to seek a few unified themes amongst diverse phenomena.

9

Perkins, L. J., B. G. Logan, G. B. Zimmerman e C. J. Werner. "Two-dimensional simulations of thermonuclear burn in ignition-scale inertial confinement fusion targets under compressed axial magnetic fields". Physics of Plasmas 20, n. 7 (luglio 2013): 072708. http://dx.doi.org/10.1063/1.4816813.

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Beurskens, M. N. A., C. Angioni, S. A. Bozhenkov, O. Ford, C. Kiefer, P. Xanthopoulos, Y. Turkin et al. "Confinement in electron heated plasmas in Wendelstein 7-X and ASDEX Upgrade; the necessity to control turbulent transport". Nuclear Fusion 62, n. 1 (14 dicembre 2021): 016015. http://dx.doi.org/10.1088/1741-4326/ac36f1.

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Abstract In electron (cyclotron) heated plasmas, in both ASDEX Upgrade (L-mode) and Wendelstein 7-X, clamping of the ion temperature occurs at T i ∼ 1.5 keV independent of magnetic configuration. The ions in such plasmas are heated through the energy exchange power as n e 2 ( T e − T i ) / T e 3 / 2 , which offers a broad ion heating profile, similar to that offered by alpha heating in future thermonuclear fusion reactors. However, the predominant electron heating may put an additional constraint on the ion heat transport, as the ratio T e/T i > 1 can exacerbates ITG/TEM core turbulence. Therefore, in practical terms the strongly ‘stiff’ core transport translates into T i-clamping in electron heated plasmas. Due to this clamping, electron heated L-mode scenarios, with standard gas fueling, in either tokamaks or stellarators may struggle to reach high normalized ion temperature gradients required in a compact fusion reactor. The comparison shows that core heat transport in neoclassically optimized stellarators is driven by the same mechanisms as in tokamaks. The absence of a strong H-mode temperature edge pedestal in stellarators, sofar (which, like in tokamaks, could lift the clamped temperature-gradients in the core), puts a strong requirement on reliable and sustainable core turbulence suppression techniques in stellarators.

11

Murari, Andrea, Emmanuele Peluso, Luca Spolladore, Jesus Vega e Michela Gelfusa. "Considerations on Stellarator’s Optimization from the Perspective of the Energy Confinement Time Scaling Laws". Applied Sciences 12, n. 6 (10 marzo 2022): 2862. http://dx.doi.org/10.3390/app12062862.

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The Stellarator is a magnetic configuration considered a realistic candidate for a future thermonuclear fusion commercial reactor. The most widely accepted scaling law of the energy confinement time for the Stellarator is the ISS04, which employs a renormalisation factor, fren, specific to each device and each level of optimisation for individual machines. The fren coefficient is believed to account for higher order effects not ascribable to variations in the 0D quantities, the only ones included in the database used to derive ISS04, the International Stellarator Confinement database. This hypothesis is put to the test with symbolic regression, which allows relaxing the assumption that the scaling laws must be in power monomial form. Specific and more general scaling laws for the different magnetic configurations have been identified and perform better than ISS04, even without relying on any renormalisation factor. The proposed new scalings typically present a coefficient of determination R2 around 0.9, which indicates that they basically exploit all the information included in the database. More importantly, the different optimisation levels are correctly reproduced and can be traced back to variations in the 0D quantities. These results indicate that fren is not indispensable to interpret the data because the different levels of optimisation leave clear signatures in the 0D quantities. Moreover, the main mechanism dominating transport, in reasonably optimised configurations, is expected to be turbulence, confirmed by a comparative analysis of the Tokamak in L mode, which shows very similar values of the energy confinement time. Not resorting to any renormalisation factor, the new scaling laws can also be extrapolated to the parameter regions of the most important reactor designs available.

12

Pankratov, Igor M., e Volodymyr Y. Bochko. "Nonlinear Cone Model for Investigation of Runaway Electron Synchrotron Radiation Spot Shape". 3, n. 3 (28 settembre 2021): 18–24. http://dx.doi.org/10.26565/2312-4334-2021-3-02.

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The runaway electron event is the fundamental physical phenomenon and tokamak is the most advanced conception of the plasma magnetic confinement. The energy of disruption generated runaway electrons can reach as high as tens of mega-electron-volt and they can cause a catastrophic damage of plasma-facing-component surfaces in large tokamaks and International Thermonuclear Experimental Reactor (ITER). Due to its importance, this phenomenon is being actively studied both theoretically and experimentally in leading thermonuclear fusion centers. Thus, effective monitoring of the runaway electrons is an important task. The synchrotron radiation diagnostic allows direct observation of such runaway electrons and an analysis of their parameters and promotes the safety operation of present-day large tokamaks and future ITER. In 1990 such diagnostic had demonstrated its effectiveness on the TEXTOR (Tokamak Experiment for Technology Oriented Research, Germany) tokamak for investigation of runaway electrons beam size, position, number, and maximum energy. Now this diagnostic is installed practically on all the present-day’s tokamaks. The parameter v┴/|v||| strongly influences on the runaway electron synchrotron radiation behavior (v|| is the longitudinal velocity, v┴ is the transverse velocity with respect to the magnetic field B). The paper is devoted to the theoretical investigation of runaway electron synchrotron radiation spot shape when this parameter is not small that corresponds to present-day tokamak experiments. The features of the relativistic electron motion in a tokamak are taken into account. The influence of the detector position on runaway electron synchrotron radiation data is discussed. Analysis carried out in the frame of the nonlinear cone model. In this model, the ultrarelativistic electrons emit radiation in the direction of their velocity v→ and the velocity vector runs along the surface of a cone whose axis is parallel to the magnetic field B. The case of the small parameter v┴/|v||| (v┴/|v|||<<1, linear cone model) was considered in the paper: Plasma Phys. Rep. 22, 535 (1996) and these theoretical results are used for experimental data analysis.

13

Annenkov, V. V., A. V. Arzhannikov, P. A. Bagryansky, A. D. Beklemishev, V. I. Davydenko, S. L. Sinitsky, D. I. Skovorodin et al. "Department of Plasma Physics of the Physics Department at Novosibirsk State University". SIBERIAN JOURNAL OF PHYSICS 17, n. 1 (18 aprile 2022): 118–41. http://dx.doi.org/10.25205/2541-9447-2022-17-1-118-141.

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The article describes the system of scientific-engineering training at the Plasma Physics Department at the Physical Department, NSU with the active participation in this process of researchers from the plasma laboratories of the Budker Institute of Nuclear Physics of the Siberian Branch of the Russian Academy of Sciences. The text gives an idea of plasma as a subject studied in this department, and then consistently reflects the following information: the history of the department, the special courses taught in the department, the subjects of undergraduate and graduate theses, the achievements of graduates of the department in the last decade. Taking into account the main topic of scientific research in the plasma laboratories of the BINP SB RAS, the text gives an overview of the work at the plasma facilities operating at the institute and outlines the prospect of creating a next-generation linear plasma trap (GDMT). Particular attention is paid to the prospect of using open magnetic systems for hot plasma confinement in relation to solving the problem of controlled thermonuclear fusion, since these systems should serve as the field of primary activity for future graduates of the Department of Plasma Physics.

14

Demina, E. V., N. A. Vinogradova, A. S. Demin, N. A. Epifanov, E. V. Morozov, A. B. Mikhailova, V. N. Pimenov, M. D. Prusakova, S. V. Rogozhkin e S. V. Shevtsov. "Simulated irradiation of 16Cr – 4Al – 2W – 0.3Ti – 0.3Y2O3 ODS steel, perspective for thermonuclear reactors in the plasma focus facility “Vikhr”". Perspektivnye Materialy 9 (2022): 12–22. http://dx.doi.org/10.30791/1028-978x-2022-9-12-22.

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A study of the radiation-thermal resistance of ferritic steel 16Cr – 4Al – 2W – 0.3Ti – 0.3Y2O3 was made. This ODS (oxide dispersion strengthened) steel is perspective for fusion applications. The “Vikhr” Plasma Focus installation was used to introduse of powerful pulsed flows of helium ions and helium plasma. The power density of a beam of fast helium ions and high-temperature helium plasma flows was ~ 108 and 107 W/cm2 at exposure times of ~ 50 and 100 ns, respectively. The number of pulses N varied in the range from 10 to 30. The rate of evaporation and radiaсtive sputtering changed slightly with an increase in the number of pulses of energy flows acting on the material and amounted to h ≈ 0.01 – 0.02 μm/puls. The irradiated surface after repeated melting under the action of a pulsed radiation-thermal load with powerful energy flows acquired a wave-like character with inclusions of dispersed micro particles of the second phase, containing mainly yttrium, oxygen, aluminum, iron, and titanium. At the same time, in contrast to the refractory metals (W, Mo, Ti) earlier under similar radiation conditions studied, no micro- and macro cracks were formed on the surface of the material facing the plasma. “Vikhr” Plasma Focus setup proved to be an effective tool for simulation testing of candidate materials with magnetic and inertial plasma confinement.

15

Kushwaha, Manvir S. "The quantum pinch effect in semiconducting quantum wires: A bird’s-eye view". Modern Physics Letters B 30, n. 04 (10 febbraio 2016): 1630002. http://dx.doi.org/10.1142/s0217984916300027.

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Those who measure success with culmination do not seem to be aware that life is a journey not a destination. This spirit is best reflected in the unceasing failures in efforts for solving the problem of controlled thermonuclear fusion for even the simplest pinches for over decades; and the nature keeps us challenging with examples. However, these efforts have permitted researchers the obtention of a dense plasma with a lifetime that, albeit short, is sufficient to study the physics of the pinch effect, to create methods of plasma diagnostics, and to develop a modern theory of plasma processes. Most importantly, they have impregnated the solid state plasmas, particularly the electron–hole plasmas in semiconductors, which do not suffer from the issues related with the confinement and which have demonstrated their potential not only for the fundamental physics but also for the device physics. Here, we report on a two-component, cylindrical, quasi-one-dimensional quantum plasma subjected to a radial confining harmonic potential and an applied magnetic field in the symmetric gauge. It is demonstrated that such a system, as can be realized in semiconducting quantum wires, offers an excellent medium for observing the quantum pinch effect at low temperatures. An exact analytical solution of the problem allows us to make significant observations: Surprisingly, in contrast to the classical pinch effect, the particle density as well as the current density display a determinable maximum before attaining a minimum at the surface of the quantum wire. The effect will persist as long as the equilibrium pair density is sustained. Therefore, the technological promise that emerges is the route to the precise electronic devices that will control the particle beams at the nanoscale.

16

Beardsley, Tim. "Thermonuclear fusion: Inertial confinement in trouble". Nature 315, n. 6022 (1 giugno 1985): 706–7. http://dx.doi.org/10.1038/315706a0.

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Gregoire, Michel. "Controlled Thermonuclear Energy. The Magnetic Confinement". Revue Générale Nucléaire, n. 1 (gennaio 1991): 21–29. http://dx.doi.org/10.1051/rgn/19911021.

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Korobkin, V. V., e M. Yu Romanovsky. "Laser thermonuclear fusion with force confinement of hot plasma". Physical Review E 49, n. 3 (1 marzo 1994): 2316–22. http://dx.doi.org/10.1103/physreve.49.2316.

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Brandon, V., B. Canaud, M. Temporal e R. Ramis. "Thermodynamic properties of thermonuclear fuel in inertial confinement fusion". Laser and Particle Beams 34, n. 3 (31 agosto 2016): 539–44. http://dx.doi.org/10.1017/s0263034616000422.

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AbstractHot-spot path in the thermodynamic space $({\rm \rho} R,T_{\rm i} )_{{\rm hs}} $ is investigated for direct-drive scaled-target family covering a huge interval of kinetic energy on both sides of kinetic threshold for ignition. Different peak implosion velocities and two initial aspect ratios have been considered. It is shown that hot spot follows almost the same path during deceleration up to stagnation whatever the target is. As attended, after stagnation, a clear distinction is done between non-, marginally-, or fully igniting targets. For the last, ionic temperature can reach very high values when the thermonuclear energy becomes very high.

20

Kolmes, E. J., I. E. Ochs e N. J. Fisch. "Wave-supported hybrid fast-thermal p-¹¹B fusion". Physics of Plasmas 29, n. 11 (novembre 2022): 110701. http://dx.doi.org/10.1063/5.0119434.

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The possibility of fusion ignition in proton–Boron11 plasma is strongly enhanced if the energy from the fusion-produced α particles is channeled to fast protons, but in an environment in which most of the protons are thermally distributed. This hybrid of thermonuclear fusion and beam-plasma fusion offers surprisingly large advantages to either purely thermonuclear or purely beam-plasma fusion, neither of which can by themselves significantly exceed the large bremsstrahlung radiation emitted by the proton–Boron11 plasma. The hybrid scheme has the potential to reduce the confinement time of the reactants that is required to achieve ignition by an order of magnitude.

21

Rose, S. J., P. W. Hatfield e R. H. H. Scott. "Modelling burning thermonuclear plasma". Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 378, n. 2184 (12 ottobre 2020): 20200014. http://dx.doi.org/10.1098/rsta.2020.0014.

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Considerable progress towards the achievement of thermonuclear burn using inertial confinement fusion has been achieved at the National Ignition Facility in the USA in the last few years. Other drivers, such as the Z-machine at Sandia, are also making progress towards this goal. A burning thermonuclear plasma would provide a unique and extreme plasma environment; in this paper we discuss (a) different theoretical challenges involved in modelling burning plasmas not currently considered, (b) the use of novel machine learning-based methods that might help large facilities reach ignition, and (c) the connections that a burning plasma might have to fundamental physics, including quantum electrodynamics studies, and the replication and exploration of conditions that last occurred in the first few minutes after the Big Bang. This article is part of a discussion meeting issue ‘Prospects for high gain inertial fusion energy (part 1)’.

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Ongena, J., R. Koch, R. Wolf e H. Zohm. "Magnetic-confinement fusion". Nature Physics 12, n. 5 (maggio 2016): 398–410. http://dx.doi.org/10.1038/nphys3745.

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Furth, H. P. "Magnetic Confinement Fusion". Science 249, n. 4976 (28 settembre 1990): 1522–27. http://dx.doi.org/10.1126/science.249.4976.1522.

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Campbell, David. "Magnetic Confinement Fusion". Europhysics News 29, n. 6 (1998): 196–201. http://dx.doi.org/10.1007/s00770-998-0196-8.

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Campbell, David. "Magnetic Confinement Fusion". Europhysics news 29, n. 6 (1998): 196. http://dx.doi.org/10.1007/s007700050091.

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Schwarzschild, Bertram. "Inertial-Confinement Fusion Driven by Pulsed Power Yields Thermonuclear Neutrons". Physics Today 56, n. 7 (luglio 2003): 19–21. http://dx.doi.org/10.1063/1.1603065.

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Atzeni, S., D. Batani, C. N. Danson, L. A. Gizzi, S. Le Pape, J.-L. Miquel, M. Perlado et al. "Breakthrough at the NIF paves the way to inertial fusion energy". Europhysics News 53, n. 1 (2022): 18–23. http://dx.doi.org/10.1051/epn/2022106.

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In August 2021, at the National Ignition Facility of the Lawrence Livermore National Laboratory in the USA, a 1.35 MJ fusion yield was obtained. It is a demonstration of the validity of the Inertial Confinement Fusion approach to achieve energy-efficient thermonuclear fusion in the laboratory. It is a historical milestone that the scientific community has achieved after decades of efforts.

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Niu, K., H. Takeda e T. Aoki. "Optimization of target for ICF and target gain". Laser and Particle Beams 6, n. 2 (maggio 1988): 149–61. http://dx.doi.org/10.1017/s0263034600003918.

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The typical target structure of the inertial confinement fusion by using the ion beams as the energy driver, and its optimized parameters are shown in this paper. The phenomenon occurring at the fuel implosion in the target, from which the thermonuclear fusion output energy of 2·5 GJ is released, is analyzed, and the requirements for the driver beam are summarized.

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Ongena, J., R. Koch, R. Wolf e H. Zohm. "Erratum: Magnetic-confinement fusion". Nature Physics 12, n. 7 (30 giugno 2016): 717. http://dx.doi.org/10.1038/nphys3818.

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Winterberg, F. "Lasers for inertial confinement fusion driven by high explosives". Laser and Particle Beams 26, n. 1 (marzo 2008): 127–35. http://dx.doi.org/10.1017/s0263034608000098.

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Proposed laser fusion power plant concepts suffer from the huge size and expense of the lasers needed for compression and ignition. In a 1969 study (classified in 1970 and declassified in 2007), the idea to use chemical high explosives for the pumping of megajoule lasers was explored. Apart from being less expensive by orders of magnitude, such lasers are expected to be much more compact, and with their large energy, output could simultaneously drive several thermonuclear micro-explosion chambers. Because of its topical importance, I accepted the journal's invitation to publish a previously classified work, but with new unpublished ideas, with the previously classified paper put into the appendix.

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Garanin, S. G., A. V. Ivanovskii, S. M. Kulikov, V. I. Mamyshev, S. N. Pevny e V. G. Rogachev. "Inertial Thermonuclear Fusion Using Explosive Magnetic Generators". Plasma Physics Reports 48, n. 2 (febbraio 2022): 111–20. http://dx.doi.org/10.1134/s1063780x22020076.

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32

Salingaros, N. A. "Magnetic Force-Free Configurations for Thermonuclear Fusion." Physics Essays 1, n. 2 (1 giugno 1988): 92–101. http://dx.doi.org/10.4006/1.3036452.

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33

Shmatov M. L. "On the problem of acceleration of fast ignition thermonuclear targets with two cones". Technical Physics 92, n. 5 (2022): 578. http://dx.doi.org/10.21883/tp.2022.05.53673.137-21.

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Abstract (sommario):

The problems of acceleration of fast ignition thermonuclear targets with two cones for their high-precision injection into region near the center of the reactor chamber are considered and the possibility of solution of these problems is shown. A brief review of discussed variants of such targets and of their main advantages, related to ignition of microexplosion and simplicity of providing preservation of targets workability during their flight in the reactor chamber, is presented. Fast ignition by microexplosion of two-sided cone target and the method to estimate acceptable speed of stabilizing rotation of thermonuclear target are proposed. Keywords: controlled thermonuclear fusion, inertial confinement, fast ignition, two-sided cone targets, spin stabilization of flight.

34

Lerche, R. A., D. Ress, R. J. Ellis, S. M. Lane e K. A. Nugent. "Neutron penumbral imaging of laser-fusion targets". Laser and Particle Beams 9, n. 1 (marzo 1991): 99–118. http://dx.doi.org/10.1017/s0263034600002366.

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Abstract (sommario):

A camera has been developed that directly measures the deuterium-tritium burn region of laser-driven inertial confinement fusion targets. Images are formed by 14-MeV thermonuclear neutrons emitted from the targets. Our demonstration instrument is based on a coded-aperture imaging technique known as penumbral imaging, and has produced images of high-yield (> 1012 neutrons) direct-drive targets with resolutions of 80 μm. The camera consists of four major components: the penumbral aperture, alignment hardware, detector system, and image analysis software.

35

Giovanielli, D. "Excimer laser development for fusion". Laser and Particle Beams 4, n. 3-4 (agosto 1986): 569–72. http://dx.doi.org/10.1017/s026303460000224x.

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Abstract (sommario):

The future utility of inertial confinement fusion requires a new driver. Successful experiments coupling laser energy to targets, and our understanding of fuel capsule behavior strongly suggest that a Laboratory thermonuclear source is attainable and power production may be considered if a suitable driver with high efficiency, high repetition rate, and most importantly, low capital cost, can be identified. No adequate driver exists today; however, the krypton fluoride laser holds great promise (Rosocha et al. 1986). By the end of this decade, driver development can be brought to the point that a technically justifiable choice can be made for the future direction of ICF.

36

Chirkov, A. Yu. "Hybrid Fusion-Fission System with Neutron Source Based on Deuterium Plasma". Herald of the Bauman Moscow State Technical University. Series Mechanical Engineering, n. 3 (132) (giugno 2020): 94–104. http://dx.doi.org/10.18698/0236-3941-2020-3-94-104.

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Abstract (sommario):

Development of hybrid fusion-fission systems appears today as a promising area in practical use of thermonuclear fusion energy. Thermonuclear plasma in such systems is the source of fast neutrons with the power gain factor Q < 1 power amplification factor in plasma. Hybrid system high amplification is generally achieved through nuclear reactions in the subcritical blanket surrounding plasma. Not only power could be produced in such a blanket, but also nuclear fuel, and waste of the nuclear fuel cycle could be disposed. The problem of systems using the thermonuclear reaction between deuterium and tritium lies in the lack of tritium reserves and in the limited possibilities of its production. Therefore, the work considers organization of a fuel cycle based on the deuterium-deuterium reaction. Options of a neutron source based on tokamak and linear system of the open trap type were examined. Magnitude of the socalled hybrid system electrical efficiency (ratio of the system electrical output to the blanket thermal power) was estimated. Calculations demonstrated fundamental possibility of realizing substantial neutron yield from deuterium plasma. To achieve acceptable performance, power gain in thermonuclear plasma should be Q = 0.5--1. In a tokamak of reasonable scale and when working on deuterium, the gain should be Q ~ 0.3. Potential advantages of linear systems associated with the possibility of high-pressure plasma confinement are presented

37

Volegov, P. L., S. H. Batha, V. Geppert-Kleinrath, C. R. Danly, F. E. Merrill, C. H. Wilde, D. C. Wilson et al. "Density determination of the thermonuclear fuel region in inertial confinement fusion implosions". Journal of Applied Physics 127, n. 8 (24 febbraio 2020): 083301. http://dx.doi.org/10.1063/1.5123751.

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38

Winterberg, F. "Thermonuclear detonation wave shaping for the fast ignitor inertial confinement fusion concept". Kerntechnik 63, n. 4 (1 aprile 1998): 202–5. http://dx.doi.org/10.1515/kern-1998-630411.

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39

Wagner, F. "Physics of magnetic confinement fusion". EPJ Web of Conferences 54 (2013): 01007. http://dx.doi.org/10.1051/epjconf/20135401007.

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40

Chen, Katherine T. "Computers Spur Magnetic Confinement Fusion". Computers in Physics 2, n. 4 (1988): 38. http://dx.doi.org/10.1063/1.4822751.

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41

Miao, Feng, Xianjun Zheng, Baiquan Deng, Wei Liu, Wei Ou e Yi Huang. "Magnetic Inertial Confinement Fusion (MICF)". Plasma Science and Technology 18, n. 11 (28 ottobre 2016): 1055–63. http://dx.doi.org/10.1088/1009-0630/18/11/01.

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42

Korobkin, V. V., e M. Yu Romanovsky. "Scaling of plasmas, heated and ponderomotively confined by powerful laser radiation". Laser and Particle Beams 16, n. 2 (giugno 1998): 235–52. http://dx.doi.org/10.1017/s0263034600011575.

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Abstract (sommario):

It is shown that a powerful laser beam is capable of the ponderomotive confinement of plasma with electron density exceeding the critical density for the radiation under review. The theory describing force and heat balances of the plasma together with the propagation of the laser radiation is developed. The laws of the dense plasma scaling for controlled thermonuclear fusion (CTF) and other applications are formulated.

43

Casey, D. T., D. B. Sayre, C. R. Brune, V. A. Smalyuk, C. R. Weber, R. E. Tipton, J. E. Pino et al. "Thermonuclear reactions probed at stellar-core conditions with laser-based inertial-confinement fusion". Nature Physics 13, n. 12 (7 agosto 2017): 1227–31. http://dx.doi.org/10.1038/nphys4220.

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44

DEUTSCH, CLAUDE, e PATRICE FROMY. "Negative pion stopping in ultra dense and hot DT targets of ICF fast ignition concern". Journal of Plasma Physics 79, n. 4 (12 febbraio 2013): 391–95. http://dx.doi.org/10.1017/s0022377813000068.

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Abstract (sommario):

AbstractIn order to implement a Scenario of π− catalysis of Deuterium–Tritium (DT) thermonuclear reactions in a dense and hot precompressed target plasma envisioned in the Intertial Confinement Fusion (ICF) fast ignition approach, we pay detailed attention to the stopping of negative pions arising from electro-disintregration of target D and T nuclei by ultra-relativistic e-beams. Emphasis is put on a mostly non-relativistic pion velocity regime (E ≤ 10 MeV).

45

Mahdavi, Mohammad, e Sayed Ebrahim Abedi. "Analytical Dependence of the Ignition Dynamics Parameters on the Low-Z Impurity Concentration". Zeitschrift für Naturforschung A 69, n. 12 (1 dicembre 2014): 645–53. http://dx.doi.org/10.5560/zna.2014-0061.

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Abstract (sommario):

AbstractIn this paper, thermonuclear burning of the deuterium-tritium (D/T) plasma of an inertial confinement fusion (ICF) target is studied in the presence of low-Z impurities (lithium, beryllium, and carbon) with arbitrary concentrations. The effect of impurities produced due to the mixing of the thermonuclear fuel with the material of the structural elements of the target during its compression on the process of target burning is studied. Also, the effect of impurity concentration on the plasma ignition parameters such as ignition temperature, confinement parameter ρR, and ignition energy are discussed. The models are constructed for an isobaric and an isochoric plasma for the case in which the burning is initiated in the central heated region of the target and then propagated into the surrounding relatively cold fuel. In ICF spherical implosions of the D/T fuel, the ignition parameters as ignition temperature and parameter ρR in the hot spot are approximately 7 - 10 keV and 0.2 - 0.4 g cm-2 respectively, and these values are increased by the presence of impurities.

46

Todd, T. N., e C. G. Windsor. "Progress in magnetic confinement fusion research". Contemporary Physics 39, n. 4 (luglio 1998): 255–82. http://dx.doi.org/10.1080/001075198181946.

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47

Weller, Arthur. "Diagnostics for magnetic confinement fusion research". Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 623, n. 2 (novembre 2010): 801–5. http://dx.doi.org/10.1016/j.nima.2010.04.009.

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48

Huang, Chuanjun, e Laifeng Li. "Magnetic confinement fusion: a brief review". Frontiers in Energy 12, n. 2 (16 febbraio 2018): 305–13. http://dx.doi.org/10.1007/s11708-018-0539-1.

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49

Ibrahim, M. U., A. Rimamsiwe, A. Musa, F. A. Umar, M. B. Abdullahi, F. Ahmad e N. F. Isa. "DEUTERON INDUCED FUSION REACTION TARGET FOR INERTIAL CONFINEMENT FUSION (ICF)". European Journal of Physical Sciences 5, n. 1 (11 marzo 2022): 25–42. http://dx.doi.org/10.47672/ejps.956.

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Abstract (sommario):

Objective: Energy efficiency enhancement is one of the most effective ways to achieve Fast ignition (FI) in inertial confinement fusion ICF. High energy output gain is essential for ICF reactors and greater energy efficiency can reduce energy costs. The injection of Ion beam is one method used to achieve FI fusion reaction in ICF. A fusion of deuteron with lithium-6 isotope, DLi6 is reviewed in this work alongside the fusion of Deuterium – Tritium (DT), Deuterium – Deuterium (DD), Deuterium – Helium-3 (DHe3) and Proton – Boron-11 (PB11). Materials and Methods: In this work, it is proposed the projection of laser-driven deuteron beam in the FI scheme for ICF in the DLi6 plasma. Fusion occurs as the projected deuteron ion beam hits the lithium-6 target in the thermonuclear fusion reaction. Results: The results show that the fusion reactions of DD, DHe3 and PB11 all require high input kinetic energy (Mega-electronvolts) for the fusion process to occur because of higher Coulomb barrier and the probability of fusion increases by increasing the input energy drive with low output energy gain. DT fusion which require low input kinetic energy of about 400 KeV with high cross section and generated considerable high output energy gain of about 17.59 MeV, However this fusion reaction require large tritium inventory and tritium does not occur naturally, therefore the need for tritium breeding. When the energy of deuteron beam is projected at 200 keV to lithium-6 isotope target, although D + Li6 has a low total cross section of about 19.409 mbarn, the stopping power of the electrons would be more than ions, nuclear stopping power is considerable at very low deuterons energies, the Coulomb interaction of deuteron and lithium-6 occurs with output energy gain of about 22.373 MeV. Conclusion: The investigations indicate that fusion target energy gain efficiency is independent of lithium-6 numerical density. The highest value of energy efficiency gain occurs with lower input kinetic energy of deuteron beam of about 200 KeV to lithium-target. Recommendation: This findings contribute to the core mission of NIF in achieving fast ignition with low ignition energy input to achieve Lawson break-even or "ignition" point of the fusion fuel pellet, where it gives off 100% or more energy than it absorbs. However the simulation results were based on programmed model of Geant4 Hadr03. This results can be validated with the appropriate experimental design of the Hadr03 process.

50

Winterberg, F. "Autocatalytic Fusion-Fission Burn in the Focus of Two Magnetically Insulated Transmission Lines". Zeitschrift für Naturforschung A 58, n. 11 (1 novembre 2003): 612–14. http://dx.doi.org/10.1515/zna-2003-1103.

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Abstract (sommario):

A configuration made up of two nested magnetically insulated transmission lines, the inner one carrying a high voltage lower current - and the outer one a high current lower voltage - pulse, was in a previous communication proposed for the ignition of a magnetic field assisted thermonuclear detonation wave. Unlike the fast ignition concept, it does not require the compression of the DT fusion fuel to densities in excess of the solid state. Here I show that with the same configuration, but by surrounding the DT fusion fuel with a blanket of solid U238, Th232 or B10, the ignition of a thermonuclear detonation wave is possible with densities of the DT fuel less than solid state densities, because the DT fusion neutrons can make a sufficient number of fission reactions, greatly increasing the pressure in the blanket, compressing the DT to high densities, launching a magnetic field assisted thermonuclear detonation wave. This autocatalytic fusion-fission burn has the further advantage that it can burn natural uranium, thorium and even boron.