ATOS: Integration of advanced technology software within distributed Spacecraft Mission Operations Systems

The Advanced Technology Operations System (ATOS) is a program of studies into the integration of advanced applications (including knowledge based systems (KBS)) with ground systems for the support of spacecraft mission operations

Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign

Tritium (T) distributions on tungsten (W)-coated plasma-facing tiles used in the third ITER-like wall campaign (2015–2016) of the Joint European Torus (JET) were examined by means of an imaging plate technique and β-ray induced x-ray spectrometry, and they were compared with the distributions after the second (2013–2014) campaign. Strong enrichment of T in beryllium (Be) deposition layers was observed after the second campaign. In contrast, T distributions after the third campaign was more uniform though Be deposition layers were visually recognized. The one of the possible explanations is enhanced desorption of T from Be deposition layers due to higher tile temperatures caused by higher energy input in the third campaign

Atomic data and modelling for fusion : the ADAS Project

The paper is an update on the Atomic Data and Analysis Structure, ADAS, since ICAM‐DATA06 and a forward look to its evolution in the next five years. ADAS is an international project supporting principally magnetic confinement fusion research. It has participant laboratories throughout the world, including ITER and all its partner countries. In parallel with ADAS, the ADAS‐EU Project provides enhanced support for fusion research at Associated Laboratories and Universities in Europe and ITER. OPEN‐ADAS, sponsored jointly by the ADAS Project and IAEA, is the mechanism for open access to principal ADAS atomic data classes and facilitating software for their use. EXTENDED‐ADAS comprises a variety of special, integrated application software, beyond the purely atomic bounds of ADAS, tuned closely to specific diagnostic analyses and plasma models. The current scientific content and scope of these various ADAS and ADAS related activities are briefly reviewed. These span a number of themes including heavy element spectroscopy and models, charge exchange spectroscopy, beam emission spectroscopy and special features which provide a broad baseline of atomic modelling and support. Emphasis will be placed on ‘lifting the fundamental data baseline’—a principal ADAS task for the next few years. This will include discussion of ADAS and ADAS‐EU coordinated and shared activities and some of the methods being exploite

Dielectronic recombination of heavy species: the tin 4p(6)4d(q)-4p(6)4d((q-1))4f+4p(5)4d((q+1)) transition arrays for q=1-10

We report on detailed calculations of dielectronic recombination (DR) rate coefficients for Sn4 +–Sn13 + using three approaches of differing degrees of complexity. These are configuration-mixed Breit–Pauli using the autostructure code, bundled-nl using the Burgess–Bethe general program (BBGP) and configuration average (CA) using the DRACULA code. We find that target Δn = 0 dipole promotions dominate the total DR rate coefficients; configuration-mixing effects are small for the totals; results for the totals are highly dependent on the initial levels averaged over—the results for averaging over all levels of the ground configuration being typically nearly a factor of 2 smaller than for using only the ground level. On comparing the total DR rate coefficients obtained using the three methods we find that the BBGP results are systematically lower than those obtained from autostructure—in some cases they are significantly lower (by a factor of 2)—while the CA results are systematically and significantly higher (by up to 80%) in general. These findings need to be borne in mind for the finite-density modelling of tin plasma sources for microlithography and tin markers for magnetic fusion plasmas especially when using simple descriptions of DR. They apply also to heavy species in general such as tungsten ions which are of great importance for magnetic fusion plasma

First principle integrated modeling of multi-channel transport including Tungsten in JET

International audienc

First principle integrated modeling of multi-channel transport including Tungsten in JET

For the first time, over five confinement times, the self-consistent flux driven time evolution of heat, momentum transport and particle fluxes of electrons and multiple ions including Tungsten (W) is modeled within the integrated modeling platform JETTO (Romanelli et al 2014 Plasma Fusion Res. 9 1-4), using first principle-based codes: namely, QuaLiKiz (Bourdelle et al 2016 Plasma Phys. Control. Fusion 58 014036) for turbulent transport and NEO (Belli and Candy 2008 Plasma Phys. Control. Fusion 50 95010) for neoclassical transport. For a JET-ILW pulse, the evolution of measured temperatures, rotation and density profiles are successfully predicted and the observed W central core accumulation is obtained. The poloidal asymmetries of the W density modifying its neoclassical and turbulent transport are accounted for. Actuators of the W core accumulation are studied: removing the central particle source annihilates the central W accumulation whereas the suppression of the torque reduces significantly the W central accumulation. Finally, the presence of W slightly reduces main ion heat turbulent transport through complex nonlinear interplays involving radiation, effective charge impact on ITG and collisionality

Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign

Tritium (T) distributions on tungsten (W)-coated plasma-facing tiles used in the third ITER-like wall campaign (2015-2016) of the Joint European Torus (JET) were examined by means of an imaging plate technique and beta-ray induced x-ray spectrometry, and they were compared with the distributions after the second (2013-2014) campaign. Strong enrichment of T in beryllium (Be) deposition layers was observed after the second campaign. In contrast, T distributions after the third campaign was more uniform though Be deposition layers were visually recognized. The one of the possible explanations is enhanced desorption of T from Be deposition layers due to higher tile temperatures caused by higher energy input in the third campaign

Overview of the JET results

Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in confinement and pedestal behaviour before and after the ITER-like wall installation have been better characterized towards the development of high fusion yield scenarios in DT. Post-mortem analyses of the plasma-facing components have confirmed the previously reported low fuel retention obtained by gas balance and shown that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon. Transport to remote areas is almost absent and two orders of magnitude less material is found in the divertor