Abstract:Abstract.A new strategic energy plan decided by the Japanese Cabinet in 2014 strongly supports the steady promotion of nuclear fusion development activities, including the ITER project and the Broader Approach activities from the long-term viewpoint. Atomic Energy Commission (AEC) in Japan formulated the Third Phase Basic Program so as to promote an experimental fusion reactor project. In 2005 AEC has reviewed this Program, and discussed on selection and concentration among many projects of fusion reactor deve… Show more
“…In this paper, an emission model is used for computing the emission spectra of the ablation clouds all along the pellet lifetime. Synthetic spectra and cloud images are built and compared with measurements of a well documented pellet 4 injected in the Large Helical Device (LHD): stellarator at the National Institute for Fusion Science, Japan [10] (it is noticeable that the characteristics of ablation clouds, which are only function of the local plasma properties, do not depend on the magnetic configuration). The first part of this paper-sections 2 and 3describes the diagnostics used in this study and the procedure for cross calibrating the data.…”
The experimental reproduction of the conditions of pellet injection expected in future large devices being
not possible in present day machines, it is mandatory to validate as thoroughly as possible the available abla-
tion models. Among the different points still under discussion, there is the relation between the spectroscopic
measurement of the ablation clouds and the local ablation rate. This relation is investigated by coupling an
emission model to the time-dependent simulation of ablation clouds with the HPI2 pellet ablation/deposition
code. The simulated quantities are the time-evolution of the cloud visible spectrum ( λ = 400 − 700 nm ) and
images in different wavelength domains (e.g. Hα, Hβ or the continuum centered at λ = 576 nm ). It is found
that the cloud emission is anisotropic, this is particularly the case for Hα and Hβ lines, and that the relation
between the cloud emission and the ablation rate depends not only on the conditions of pellet injection, but also
on the direction of observation. It follows that, in general, it is not possible to estimate the ablation profile from
that of an emission line (Hα or Hβ ). The code predictions are compared with corresponding measurements for
a welldocumented pellet injected in LHD, showing a good agreement for global values and main trends. The
reasons for observed discrepancies are discussed.
“…In this paper, an emission model is used for computing the emission spectra of the ablation clouds all along the pellet lifetime. Synthetic spectra and cloud images are built and compared with measurements of a well documented pellet 4 injected in the Large Helical Device (LHD): stellarator at the National Institute for Fusion Science, Japan [10] (it is noticeable that the characteristics of ablation clouds, which are only function of the local plasma properties, do not depend on the magnetic configuration). The first part of this paper-sections 2 and 3describes the diagnostics used in this study and the procedure for cross calibrating the data.…”
The experimental reproduction of the conditions of pellet injection expected in future large devices being
not possible in present day machines, it is mandatory to validate as thoroughly as possible the available abla-
tion models. Among the different points still under discussion, there is the relation between the spectroscopic
measurement of the ablation clouds and the local ablation rate. This relation is investigated by coupling an
emission model to the time-dependent simulation of ablation clouds with the HPI2 pellet ablation/deposition
code. The simulated quantities are the time-evolution of the cloud visible spectrum ( λ = 400 − 700 nm ) and
images in different wavelength domains (e.g. Hα, Hβ or the continuum centered at λ = 576 nm ). It is found
that the cloud emission is anisotropic, this is particularly the case for Hα and Hβ lines, and that the relation
between the cloud emission and the ablation rate depends not only on the conditions of pellet injection, but also
on the direction of observation. It follows that, in general, it is not possible to estimate the ablation profile from
that of an emission line (Hα or Hβ ). The code predictions are compared with corresponding measurements for
a welldocumented pellet injected in LHD, showing a good agreement for global values and main trends. The
reasons for observed discrepancies are discussed.
“…In the case of ICF with direct-drive targets, shrapnel is not a concern, but the buffer gas is incompatible with target cryogenics during injection [11]. Alternative solutions [12] have been proposed, such as magnetic intervention [13] or wetted wall concepts [14,15]. Many years after the first proposals of wetted walls [16], aspects like the formation of aerosols, the vapour pressure inside the chamber or the maintenance of a liquid layer over all the internal surfaces of the chamber remain unaddressed [17], despite their paramount importance for this approach.…”
Plasma-facing materials (PFMs) for nuclear fusion, either in inertial confinement fusion (ICF) or in magnetic confinement fusion (MCF) approaches, must withstand extremely hostile irradiation conditions. Mitigation strategies are plausible in some cases, but usually the best, or even the only, solution for feasible plant designs is to rely on PFMs able to tolerate these irradiation conditions. Unfortunately, many studies report a lack of appropriate materials that have a good thermomechanical response and are not prone to deterioration by means of irradiation damage. The most deleterious effects are vacancy clustering and the retention of light species, as is the case for tungsten. In an attempt to find new radiation-resistant materials, we studied tungsten hollow nanoparticles under different irradiation scenarios that mimic ICF and MCF conditions. By means of classical molecular dynamics, we determined that these particles can resist astonishingly high temperatures (up to ∼3000 K) and huge internal pressures (>5 GPa at 3000 K) before rupture. In addition, in the case of gentle pressure increase (ICF scenarios), a self-healing mechanism leads to the formation of an opening through which gas atoms are able to escape. The opening disappears as the pressure drops, restoring the original particle. Regarding radiation damage, object kinetic Monte Carlo simulations show an additional self-healing mechanism. At the temperatures of interest, defects (including clusters) easily reach the nanoparticle surface and disappear, which makes the hollow nanoparticles promising for ICF designs. The situation is less promising for MCF because the huge ion densities expected at the surface of PFMs lead to inevitable particle rupture.
“…The principle of the Japanese fusion research and development activities is laid down in the 'Third Phase Basic Program of Fusion Research and Development' [8] formulated by the Atomic Energy Commission in Japan, which was released in June 1992. The achievement of the self-ignition condition, the demonstration of long pulse (1000 s) burning plasma and the development of fundamental fusion technology necessary for DEMO are the main targets.…”
The JT-60SA project has been implemented for the purpose of an early realization of fusion energy. With a powerful and versatile NBI and ECRF system, a flexible plasma-shaping capability, and various kinds of in-vessel coils to suppress MHD instabilities, JT-60SA plays an essential role in addressing the key physics and engineering issues of ITER and DEMO. It aims to achieve the long sustainment of high integrated performance plasmas under the high βN condition required in DEMO. The fabrication and installation of components and systems of JT-60SA procured by the EU and Japan are steadily progressing. The installation of toroidal field (TF) coils around the vacuum vessel started in December 2016. The commissioning of the cryogenic system and power supply system has been implemented in the Naka site, and JT-60SA will start operation in 2019. The JT-60SA research plan covers a wide area of issues in ITER and DEMO relevant operation regimes, and has been regularly updated on the basis of intensive discussion among European and Japanese researchers.
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