“…HL-2M device will be a non-circular cross-section tokamak with a high elongation of about 2. During operation the plasma current may be rapidly reduced to zero as a consequence of loss of confinement or impurity influx [3,4] . If the plasma current quench takes place in a short time with no significant vertical displacement, this kind of phenomenon can be referred to as major disruptions (MDs).…”
For a robust design of vacuum vessel of HL-2M, the electromagnetic (EM) loads have to be understood clearly. In this paper, some crucial transient events, such as plasma major disruptions (MDs), vertical displacement events (VDEs), fast discharge of toroidal field (TF) coils, have been investigated to evaluate the eddy currents and EM forces on vacuum vessel and in-vessel components. The results show that the eddy currents depend strongly on the current decay time, and the maximum toroidal eddy current flowing in the whole vessel can reach up to 2.4 MA during MDs that is close to the plasma current. Large symmetric radial forces and a net vertical force on vessel shells could be caused by these transient events. Combination of eddy currents in in-vessel components and toroidal field could twist the copper plates and other internal parts, however, if these plates are supported and connected carefully, the twist moments will not have a big effect on the vessel shells and vessel support.
“…HL-2M device will be a non-circular cross-section tokamak with a high elongation of about 2. During operation the plasma current may be rapidly reduced to zero as a consequence of loss of confinement or impurity influx [3,4] . If the plasma current quench takes place in a short time with no significant vertical displacement, this kind of phenomenon can be referred to as major disruptions (MDs).…”
For a robust design of vacuum vessel of HL-2M, the electromagnetic (EM) loads have to be understood clearly. In this paper, some crucial transient events, such as plasma major disruptions (MDs), vertical displacement events (VDEs), fast discharge of toroidal field (TF) coils, have been investigated to evaluate the eddy currents and EM forces on vacuum vessel and in-vessel components. The results show that the eddy currents depend strongly on the current decay time, and the maximum toroidal eddy current flowing in the whole vessel can reach up to 2.4 MA during MDs that is close to the plasma current. Large symmetric radial forces and a net vertical force on vessel shells could be caused by these transient events. Combination of eddy currents in in-vessel components and toroidal field could twist the copper plates and other internal parts, however, if these plates are supported and connected carefully, the twist moments will not have a big effect on the vessel shells and vessel support.
“…Electromagnetic force due to magnet quench (F2): ~~~~~h of the magnet is one of the special abnormal Fig. 4 Distribution of the eddy current and electromagevents for the superconducting tokamak device. Once netic force On vacuum it happens, the quench of the toroidal field induces an (a) Induced eddy current On vacuum due plasma eddy current on the vacuum vessel and the coupling disruption; (b) Electromagnetic force on vacuum vessel due of the current with the background magnetic field will to plasma disruption (Unit:~10-' M ~a ) produce an electromagnetic force on the vacuum vessel.…”
EAST (experimental advanced superconducting tokamak) is an advanced steadystate plasma physics experimental device, which is being constructed as the Chinese National Nuclear Fusion Research Project. During the plasma operation the vacuum vessel as one of the key component will withstand the electromagnetic force due to the plasma disruption, the Halo current and the toroidal field coil quench, the pressure of boride water and the thermal load due to 250°C baking by pressurized nitrogen gas. In this paper a report of the static and dynamic mechanical analyses of the vacuum vessel is made. Firstly the applied loads on the vacuum vessel were given and the static stress distribution under the gravitational loads, the pressure loads, the electromagnetic loads and thermal loads were investigated. Then a series of primary dynamic, buckling and fatigue life analyses were performed to predict the structure's dynamic behavior. A seismic analysis was also conducted.
“…In the baking state, the repetition number was estimated from 25 times baking a year with the maximum baking temperature of 130°C. The repetition number of the plasma disruption is 10,000, which means 20% provability of plasma disruption for 10 years plasma operation [5]. The repetition number for the seismic during the baking was estimated based on the facts that the earthquake continues for 10 seconds with 0.…”
The vacuum vessel of the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak has 72 ports for diagnostics, plasma heating, vacuum pumping, baking, and cooling. And the design and fabrication of the bellows at each port need special care in order to compensate relative displacement between the vacuum vessel and the cryostat. S-type welded bellows were designed based on the port shape, the maximum displacement, and the life cycle. Fatigue strength evaluation using Minor's rule was performed. Rectangularshaped prototype bellows with outer dimension of 1370 mm x 1610 mm was fabricated and tested. We confirmed that the bellows had sufficient fatigue strength and vacuum reliability. VALQUA fabricated the bellows including one prototype bellows and 72 main bellows. The fabricated bellows were assembled with the vacuum vessel ports. The assembled port devices are going to be welded on the vacuum vessel body in accordance with the KSTAR tokamak assembly scenario.
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