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Thermo-mechanical analysis of Wendelstein 7-X plasma facing components

TLDR
In this paper, the authors present detailed FE thermo-mechanical analyses of a prototype high heat flux (HHF) target module, baffles, heat shields and wall panels, as well as benchmarking against tests.
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This article is published in Fusion Engineering and Design.The article was published on 2013-10-01 and is currently open access. It has received 13 citations till now. The article focuses on the topics: Wendelstein 7-X & Divertor.

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Citations
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Journal ArticleDOI

Engineering design for the magnetic diagnostics of Wendelstein 7-X

TL;DR: The Wendelstein 7-X (W7-X) stellarator as discussed by the authors was designed as a pick-up coil to measure the toroidal plasma current, saddle coils to measure Pfirsch-Schluter currents, and segmented Rogowski coils (poloidal magnetic field probes) to add information on the distribution of the plasma current density.
Journal ArticleDOI

Specific Features of Wendelstein 7-X Structural Analyses

TL;DR: The Wendelstein 7-X modular stellarator is in the final assembly phase at the Max Planck Institute for Plasma Physics in Greifswald, Germany, and the focus of the numerical analysis has been shifted toward fast consideration of nonconformities and changes in assembly procedures.
Journal ArticleDOI

Status of High Heat Flux Components at W7-X

TL;DR: The divertor of the stellarator Wendelstein 7-X was designed for high heat fluxes (HHFs) as mentioned in this paper, which is a set of 10 target and baffle units arranged along the plasma surface, and the divertor target elements, which are based on flat carbon-carbon fiber composite tiles bonded via active metal casting onto CuCrZr cooling structures required intensive development and testing to reach a reliable performance.
Journal ArticleDOI

Detecting divertor damage during steady state operation of Wendelstein 7-X from thermographic measurements.

TL;DR: A method is presented for an early detection of fatigue failures of the interface layer, solely by using the information delivered by the IR-cameras monitoring the divertor.
References
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Journal ArticleDOI

The Capabilities of Steady State Operation at the Stellarator W7-X with Emphasis on Divertor Design

TL;DR: The Wendelstein 7-X (W7-X) as discussed by the authors is a large HELIAS type stellarator that is currently under construction at Greifswald, Germany, and the start of operation is planned in 2006.
Journal ArticleDOI

The in-vessel components of the experiment Wendelstein 7-X

TL;DR: The main components of the open divertor are the vertical and horizontal target plates which form the pumping gap, the cryo-vacuum pumps and the control coils as discussed by the authors.
Journal ArticleDOI

Progress in the design and development of a test divertor (TDU) for the start of W7-X operation

TL;DR: The TDU as discussed by the authors is an adiabatically cooled, reduced pulse length device that will allow machine operation over a comparable range of plasma configurations as the final long pulse high-heat flux (HHF) divertor, which will be installed after two years operation.
Journal ArticleDOI

Design and technological solutions for the plasma facing components of WENDELSTEIN 7-X

TL;DR: In this article, an advanced technology was developed in collaboration with industry for the target elements of the high heat flux (HHF) divertor, the so-called "bi-layer" technology for the bonding of flat tiles made from CFC NB31 onto the CuCrZr cooling structure.
Journal ArticleDOI

Final design of W7-X divertor plasma facing components—tests and thermo-mechanical analysis of baffle prototypes

TL;DR: In this paper, the design of the target plates, baffle plates and wall protection for the W7-X divertor PFCs is presented. And the experimental results are compared with finite element calculations of the temperature and stress distributions in the elements.
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Q1. What contributions have the authors mentioned in the paper "Thermo-mechanical analysis of wendelstein 7-x plasma facing components" ?

The paper presents detailed FE thermo-mechanical analyses of a prototype HHF target module, baffles, heat shields and wall panels, as well as benchmarking against tests. 

due to high thermal stress in the cooling pipes, the pulse length of plasma operation must be limited depending on the number of full load cycles. 

Large expansion and deformation during baking and plasma operation due to heat loads, internal pressure, and PV deformation were considered. 

The TEs are fully fixed to the support rail at the side where they are connected to the cooling pipes, while at the other side they can slide radially relative to the other support rail. 

An important issue is the definition of gaps required between WPs in order to avoid collisions and overload of the supports to the PV. 

The normal plasma operation load case includes 100 kW/m 2 heat load, 5813 W/m 2 K heat transfer coefficient in the cooling channel at constant cooling water temperature of 80 °C, and 2 MPa cooling water pressure. 

The stellarator experiment W7-X being constructed in Greifswald, Germany, is designed for stationary plasma operation (30 min) with steady state heating of up to 10 MW ECRH and 10 s pulse heating power of up to 20 MW with additional NBI and ICRH [1]. 

Two significant issues were found in the course of analyses: (1) the large temperature gradient in the pipe results in high stresses and (2) the cooled but still rather hot back surfaces of graphite tiles lead to heat loads on the PV significantly exceeding the design limit. 

In order to predict the operation limit of W7-X more precisely, further heat flux tests with an increased number of cycles are necessary. 

They are being installed in the PV in order to protect it and other in-vessel components behind them from the convectional/radiative heat coming from the plasma. 

The maximum stresses in the cooling pipes, manifolds, manifold supports, stiff beam and frame are 209 MPa, 348 MPa, 279 MPa, 138 MPa and 314 MPa, respectively. 

FE calculations indicate that the tiles of baffles and heat shields can withstand average steady state heat loads of 250 kW/m 2 . 

In the elastic calculation of load case 1, von-Mises stresses in the support rails are higher than 1000 MPa in a large area, which is far beyond the limit of 525 MPa (secondary stress limit 3Sm) for SS EN 1.4435 at 70 °C. 

A 3D global FE model as shown in figure 2 was created for TM-H09 to perform thermo-mechanical analyses with the main purpose to estimate deflections, thermal stresses and requirements for module attachment. 

Based on this information, the gap requirements to be checked during assembly were defined in toroidal and poloidal directions separately, depending on the curvature of the WPs, the distances between all relevant support pairs of a series of WPs, and the available sliding space between the panels and their supports. 

The results showed that the tile can withstand the average heat load for steady state operation, but that under local peak heat load it can only be operated in pulses of up to 45 s to limit the thermal stress in the cooling pipe. 

The thermal calculation shows that the maximum temperatures of the CFC tiles, interlayers and CuCrZr heat sinks are 911 °C, 481 °C and 321 °C, respectively, which correspond to the experimental results [11]. 

Assuming all of them to be full load cycles, the allowed pulse length of a local peak heat load would be 40 s which is coincidentally consistent with the result of FE elastic analysis of a single tile. 

Further analyses are ongoing on the baffles, heat shields and wall panels with respect to allowed gaps and steps in between them, relaxation of support restrictions, and non-conformities. 

On the other hand, the edge tiles are less critical with respect to thermal deformation of the cooling pipe, which is less restrained in such tiles than in the tiles in the middle of the module.