Design and verification status of COMPASS-U vacuum vessel and stabilization loop
Introduction
The COMPASS-U is a new medium-sized (R = 0.894 m, a = 0.27 m) tokamak with high magnetic field (Bt = 5 T) and high temperature (< 500 °C) operation. It is designed to address key challenges related to plasma exhaust, liquid metal divertor, enhanced confinement modes and edge plasma physics important for the next-step devices [1]. Fig. 1 shows the geometrical arrangements of the major components of the tokamak. The Poloidal Field (PF) coils and Central Solenoids (CS) are placed surrounding the Vacuum Vessel (VV) and inside the demountable Toroidal Field (TF) coils. The vacuum vessel is supported on the external support structure [2].
The COMPASS-U is designed to operate with 2 MA plasma current and 5 T toroidal magnetic field, hence strong eddy currents can be induced in the VV and surrounding passive structures during a plasma disruption event. Interaction of the induced current with the magnetic field generates large electromagnetic forces on the systems. The COMPASS-U VV design is mainly based on the electromagnetic forces produced during plasma disruption events and several FE simulations are carried out for different load combinations to ensure its structural integrity.
A number of design changes take place during progress of the VV design from the conceptual design study [3]. The wall thickness of the VV shell is reduced, corner ribs are replaced by forged ring and equatorial port height is reduced to 500 mm to keep clearance between port and PF4 during thermal movement. The design of the Passive Stabilizinging Plate, PSP support and PSP bridge are also added in the vessel. The VV support design is optimized through a series of FE simulations.
Section snippets
Vacuum vessel design description
The arrangement of the VV system and its assembly consisting of main vessel, port extensions, VV support, PSP and its support on VV are as shown in Fig. 1. The vacuum vessel has to provide a first confinement barrier, a high-quality vacuum, a high toroidal resistance, a reliable structural boundary for the lifetime of the machine and remove heat from the in-vessel component. The vacuum vessel also has to support the in-vessel components and withstand design loads, high normal & off-normal
Plasma disruption forces and electromagnetic model
During plasma disruptions, electromagnetic forces are induced by time-varying eddy current in the VV. These electromagnetic forces are the most important loads for COMPASS-U VV structural design and mechanical analysis. Transient analysis of the plasma disruption is used to calculate induced eddy currents in the vessel, which interact with the toroidal & poloidal magnetic fields and cause electromagnetic forces on the vessel structure as a result.
A non-selfconsistent engineering approach to
Thermo-mechanical analyses
Thermo-mechanical analyses are carried out to examine the behavior of the proposed VV design under the plasma disruption loads and to find out the worst load combinations for the system. The mechanical verification is carried out using a 3D model of 45-degree sector consisting of main vessel, PSP, back plate with rib support and VV flexible plates support as shown in Fig. 5(a). The FE verification using non-linear elastic analysis is carried out for assessment of the vessel stresses. In
Summary
The paper summarizes the proposed preliminary mechanical design of the COMPASS-U vacuum vessel and passive stabilization loop. Mechanical verification is carried out for the several load combinations and the worst load combinations are identified for the system. The present VV design is developed on the base of the proposed critical disruption sequences. Results show that the main vessel is within the safe material stress limit. The FE model shows high stresses in the PSP, in places where PSP
Declaration of Competing Interest
None.
Acknowledgments
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.
The authors would like to acknowledge the support of A. Brooks, P. Titus and PPPL team for their support during COMPASS-U design under collaboration between IPP CAS and PPPL for COMPASS Upgrade project, The work was funded by the U. S. Department of Energy contract no.
References (15)
Conceptual design of the COMPASS upgrade tokamak
Fusion Eng. Des.
(2017)Electromagnetic model for finite element analyses of plasma disruption events used in the design phase of the COMPASS-U tokamak
Fusion Eng. Des.
(2021)Design and manufacturing of JT-60SA vacuum vessel
Fusion Eng. Des.
(2011)- P. Vondracek et al., “Preliminary Design of the COMPASS Upgrade Tokamak” in this...
design study of vacuum vessel concepts for compass-u tokamak
- Inconel-625 material data,...
- Inconel-625 material data,...