ALPHYSICA GmbH

Karlsruhe, Germany

ALPHYSICA GmbH

Karlsruhe, Germany
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Alekseev A.B.,ITER Organization | Amoskov V.M.,JSC NIIEFA | Bazarov A.M.,JSC NIIEFA | Belov A.V.,JSC NIIEFA | And 7 more authors.
Fusion Engineering and Design | Year: 2017

The paper presents an attempt to proceed to a general concept of software environment for fast and consistent multi-task simulation of EM transients (engineering simulator for tokamak applications). As an example, the ITER tokamak is taken to introduce a computational technique. The strategy exploits parallel processing with optimized simulation algorithms based on using of influence functions and superposition principle to take full advantage of parallelism. The software has been tested on a multi-core supercomputer. The results were compared with data obtained in TYPHOON computations. A discrepancy was found to be below 0.4%. The computation cost for the simulator is proportional to the number of observation points. An average computation time with the simulator is found to be by hundreds times less than the time required to solve numerically a relevant system of differential equations for known software tools. © 2017 Elsevier B.V.


Belov A.,ALPHYSICA GmbH | Gapionok E.,ALPHYSICA GmbH | Gornikel I.,ALPHYSICA GmbH | Kukhtin V.,ALPHYSICA GmbH | And 3 more authors.
Fusion Engineering and Design | Year: 2011

Transient electromagnetic (EM) analysis is presented focusing on main components of the ITER core charge exchange recombination spectroscopy (cCXRS) port plug developed by Forschungszentrum Jülich (FZJ), ITER-NL and UKAEA(CCFE) in 2009. The cCXRS primary function is to transfer the light in the visible part of spectra emitted by interaction of the plasma ions with a diagnostic neutral beam. The TYPHOON software package has been used for the EM analysis. The code is dedicated for simulation of transient electromagnetic processes using a shell approach in the integral-differential formulation to represent conducting structures with a set of multi-connected shells arbitrary located in a space. The advantage of the shell approach is a higher flexibility in modelling detailed structures as compared with widely used 3D models. On the other hand, the shell approach requires ultimate care in modelling relatively thick structures. These issues are discussed in the paper. Two vertical displacement events (VDE) which seem to result in the largest EM loads on the main cCXRS components have been agreed with FZJ and simulated. Transient electromagnetic processes caused by different sources have been considered separately, and then superimposed to obtain the total solution. Three types of transient processes for each type of VDE have been analyzed: (1) due to variations of a toroidal plasma current, shape and position and due to variations of poloidal field coils (PFC) and central solenoid (CS) currents, (2) due to variations of the Halo current and (3) due to variations of a toroidal magnetic flux of plasma. The analysis covers two options for electrical contact between the main shell (MS) of the port plug and the blanket shield module (BSM). The results are supposed to be used for benchmarking with independent 3D EM models developed for the upper port plug. © 2011 Elsevier B.V. All rights reserved.


Senik K.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Grigoriev S.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Tanchuk V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Gornikel I.,ALPHYSICA GmbH | And 4 more authors.
Fusion Engineering and Design | Year: 2013

The ITER core charge exchange recombination spectroscopy (core CXRS) is a diagnostic system designed to collect the light emitted from interaction of the Diagnostic Neutral Beam (DNB) with the core plasma and guides it via a mirror labyrinth through the Upper Port Plug toward a fiber bundle, which then transmits the light to a set of spectrometers for spectral analysis. The first mirror (M1), being the most important part of the optical system which defines workability of the entire CXRS, works in direct view of the plasma. The latter strongly impacts the mirror causing its surface erosion and deposition with degradation of the optical capability. The fast shutter (FS) is supposed to play the main role in reducing the time of the first mirror exposition to the plasma. The performed work is focused on the detailed thermal and hydraulic analyses of the main components of the M1 protecting device (blades, arms and actuator) and its cooling and pneumatic systems. The performed analysis confirms, in general, the workability of the helium-operated shutter and verifies the pneumatic actuation concept proposed for the M1 protecting device. © 2013 Elsevier B.V. All rights reserved.


Chang H.-S.,ITER Organization | Forgeas A.,ITER Organization | Vincent G.,ITER Organization | Maekawa R.,ITER Organization | And 7 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2012

One of the main challenges of the ITER cryogenic system is to manage the large pulsed heat load variation generated by the superconducting magnet system during the fusion experiments. A solution proposed to smooth such pulses and verified by numerical simulations is to use the ITER magnet structure (ST) system as a thermal buffer by taking advantage of its large mass of about 5,000 tons and consequent thermal inertia. In order to validate the simulated predictions, tests have been executed on existing cryogenic facilities. © 2011 IEEE.


Alekseev A.,ITER Organization | Arslanova D.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Belov A.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Belyakov V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | And 10 more authors.
Fusion Engineering and Design | Year: 2013

A set of detailed computational models are reviewed that covers integrally the system "vacuum vessel (VV), cryostat, and thermal shields (TS)" to study transient electromagnetics (EMs) in the ITER machine. The models have been developed in the course of activities requested and supervised by the ITER Organization. EM analysis is enabled for all ITER operational scenarios. The input data are derived from results of DINA code simulations. The external EM fields are modeled accurate to the input data description. The known magnetic shell approach can be effectively applied to simulate thin-walled structures of the ITER machine. Using an integral-differential formulation, a single unknown is determined within the shells in terms of the vector electric potential taken only at the nodes of a finite-element (FE) mesh of the conducting structures. As a result, the FE mesh encompasses only the system "VV + Cryostat + TS". The 3D model requires much higher computational resources as compared to a shell model based on the equivalent approximation. The shell models have been developed for all principal conducting structures in the system "VV + Cryostat + TS" including regular ports and neutral beam ports. The structures are described in details in accordance with the latest design. The models have also been applied for simulations of EM transients in components of diagnostic systems and cryopumps and estimation of the 3D effects of the ITER structures on the plasma performance. The developed models have been elaborated and applied for the last 15 years to support the ITER design activities. The finalization of the ITER VV design enables this set of models to be considered ready to use in plasma-physics computations and the development of ITER simulators. © 2013 Elsevier B.V.


Arslanova D.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Belyakov V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Bessette D.,ITER Organization | Gornikel I.,ALPHYSICA GmbH | And 5 more authors.
Fusion Engineering and Design | Year: 2013

Normal operation of the ITER TF coils at 15 MA reference scenario is simulated with the use of the VENECIA code. The developed numerical model adopts a full scale quasi 3D approach for thermal hydraulic and thermal diffusion analysis of TF coils at the reference scenario with greatly variable heat loads from nuclear heating and Eddy/AC losses. The model implements latest heat load specifications and corrective changes in design of TFWP, TF case and their cryogenic circuits. For the first time the primary auxiliary cryogenic boxes (ACBs) are included in a common model to provide for the forced-flow cooling of the TF winding, TF case together with CS/OIS structures and PF supports. © 2013 Elsevier B.V.


Amoskov V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Belyakov V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Egorov S.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Firsov A.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | And 11 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2011

A feasibility has been demonstrated for numerical reconstruction of geometrical displacement or deformations of the winding occurred in the manufacture and assembly of magnet coils using magnetic measurements, that is one of the principal issues for the quality control of the magnet. For validations of the proposed approach, test results of reconstruction of possible misalignments and deviations of the ITER coil are presented. The method described is applicable for a variety of coils. © 2011 IEEE.

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