Concept of the bolometry diagnostics design for COMPASS-Upgrade

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Abstract

The COMPASS-Upgrade tokamak, being designed as a medium-sized tokamak, operating with a hot first wall, allows for the study of DEMO-relevant plasma exhaust physics, crucial for future reactors. Bolometry diagnostics for COMPASS-U, consisting of metal foil bolometers and AXUV diodes, are proposed to measure spatially- and time-resolved radiation losses. Metal foil bolometers supply the absolute value of radiation power, whereas the AXUV diodes can observe fast phenomena such as MHD activity. Coverage of the whole poloidal cross-section by bolometers’ cameras allows tomography reconstruction of the local plasma emissivity. The metallic foil bolometry system will be based on sensors with a gold absorber on a silicon nitride substrate with a platinum resistor. Special modifications, e.g., channel separation, will be applied to the detectors to fulfil the requirements. Due to the high temperature, effective thermal shielding and cooling are essential to reduce the risk of damage to the detectors as well as reducing noise in the measured signal. The pin-hole cameras spatial configuration was optimized to provide the best performance under the given engineering constraints. The position of the cameras strongly depends on the space available behind the plasma-facing components (PFC). The proposed layout allows for an efficient observation of the confined plasma as well as that of the divertor region.

Introduction

The COMPASS-Upgrade will be a medium size tokamak developed for a flexible operation at extremely high heat fluxes of order of 100 MW/m2. The COMPASS-U will provide an operation with a strong magnetic field up to 5 T, plasma current up to 2 MA, and high densities up to 3∙1020 m3. Additionally, the tokamak will have its metallic first wall maintained at high temperatures (200 °C – 500 °C) during a high-performance operation, being able to modify recycling and/or to handle liquid metals when tested such divertor modules. Due to these unique capabilities, the COMPASS-U will allow for the study of reactor-relevant plasma exhaust physics, high-temperature operation, and advanced confinement scenarios providing a promising outlook for ITER and DEMO. The upper and lower closed divertors will provide the capability of studying different divertor configurations (single null, double null, snowflake, etc.) with extreme heat fluxes [1].

Power losses, which are an essential part of the power balance in plasma, are connected to the conductive losses at the first wall, electromagnetic radiation and nuclear reactions. The plasma radiation is a parameter carrying valuable information about plasma performance and its connected physics-based processes. It is important to monitor the plasma radiation especially during disruptions and other instabilities. In the COMPASS-U, the radiation power will be observed by the bolometry system consisting of both the metallic foil bolometers and AXUV diodes. The metallic foil bolometers will provide the absolutely calibrated measurement of the power radiated by the plasma. In the COMPASS-U, four-channel bolometers with gold absorber on silicon nitride (Si3N4) and platinum resistor [2] will be used. The sensors with a 6 μm absorber are sensitive to electromagnetic radiation of a range from 2 eV to 10 keV as well as to fast neutrals. A loss of measurement efficiency is observed at low energies due to reflections from the gold surface. The carbon coating on the sensors can significantly improve the sensitivity below 2 eV [3]. The use of carbon in the COMPASS-U vacuum vessel is forbidden for all plasma facing components but the thin coating applied on the cameras should not impact the operation, and therefore an exception might be obtained. The gold on the Si3N4 bolometers is radiation hard and allows for a relatively quick measurement (time resolution ∼ ms). The most prominent advantage of this type of detector is the possibility of self-calibration between shots and the presence of the reference sensor, which makes the detector insensitive to the temperature fluctuations in the tokamak environment. Use of the detectors with specifications tested for ITER [4], e.g., specially prepared ceramic housing without connectors influenced on the silicon plate, increases the recommended operational temperatures up to 250 °C. At temperatures higher than 300 °C drifts, and failures are observed for detectors with Si3N4 substrate [2,4].

The AXUV diodes system implemented as fast bolometry (time resolution ∼ 1 μs) will be partially restored from the AXUV diagnostic at the COMPASS [5] as it will use the photodiode array AXUV20ELG, containing 20 channels in a small space (32 × 10 × 7.5 mm). These n-on-p diodes can measure radiation from 1.1 eV, but approximately constant responsivity is only for energies above 200 eV. The spectral sensitivity in the UV region is connected to the passivation layer, and it is the main reason limiting AXUV diodes application as true bolometers. Nevertheless, correction factors for the diodes can be estimated with the use of metallic foil bolometers. For the AXUV diode, the maximum baking temperature is also 200 °C, but the operating temperature is below 80 °C [6]. Spatially resolved, line-integrated measurement by both types of detectors allows for the 2D emissivity profile reconstruction. The metallic foil bolometers will focus on slower phenomena such as a detachment regime. The AXUV diodes will monitor mainly fast events, e.g. MHD activity and disruptions.

The diagnostics field of view will cover the entire plasma volume in one poloidal plane. The additional AXUV diode cameras will be placed at two other toroidal positions for monitoring toroidal asymmetries. The systems are divided into a confined plasma part and a divertor part. Both parts separately need to provide the reconstruction of the radiation profile in the area of interest. The measurement will be performed during the entire shot. The plasma studies require the performance of the highest possible quality, which is limited by technical constraints. Degradation of AXUV diodes at all toroidal positions will be monitored using an external calibration tool.

Section snippets

Technical constraints

The most significant technical constraint is the requirement to minimise the size of the openings in the Plasma Facing Components (PFC), therefore, the collimation aperture will be shared by all channels in one camera. The pinhole camera type reduces the number of needed holes. The coverage of the whole plasma poloidal cross-section requires placing the cameras with a pinhole as close as possible to the PFCs. This setup creates a broad field of view without a need for large openings in the PFC,

Camera concept

The cameras will be placed inside the vacuum vessel behind the PFCs, therefore, they require preparation for the extreme environment. The camera walls will include a collimating aperture, cooling system, thermal insulation, and radiation shielding. The schematic drawing of the camera concept that is currently in the development stage is presented in Fig. 2. All cameras are based on the pinhole aperture. The exact form of the openings needs to be optimised for high collimation performance and a

Electronic system

The data acquisition system responsible for controlling the detectors will be placed in the diagnostic room, approximately 40 m from the cameras. There will be two types of cables in order to meet the requirements, inside and outside the vessel. Both diagnostics need low-voltage, twisted pairs of wires. The multi-wire cables can help in the reduction of the occupied space. The metallic foil bolometers need four wires per channel and the AXUV diodes need twenty wires per detector. Additional

System architecture and tomography

The geometrical configurations in the poloidal plane (layout) of both bolometric systems are selected from many possibilities in order to achieve a high quality of the tomographic reconstruction under engineering constraints. The exact position relative to PFCs can alter slightly, but the distribution of the channels line of sights (LOS) in the plasma will be approximately recreated with required modifications. The exact toroidal distribution of all diagnostics on the COMPASS-U has not yet been

Summary

The very high temperature of the COMPASS-U first wall makes the design of the plasma diagnostics very challenging. The concept of the design is proposed, but the selected technical solutions need to be tested, and relevant sophisticated engineering simulations performed. The estimations are promising, but alternative solutions are yet to be considered. The plan for the near future is the experimental testing of the thermal insulation and cooling performance. The exact positioning and placement

Declaration of Competing Interest

The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.

Acknowledgements

This work has been carried out within the framework of the project COMPASS-U: Tokamak for cutting-edge fusion research (No. CZ.02.1.01/0.0/0.0/16_019/0000768) and co-funded from European structural and investment funds.

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