Analysis of discharge scenarios in the T-15 tokamak

Diamagnetic diagnostics of rapid events in the T-15MD tokamak

“…The initial equilibrium configuration inside the vacuum vessel is shown in figure 1. This corresponds to standard T-15MD geometry [35][36][37][38][39][40][41][42][43][44][45][46][47] with major radius R 1.58 0 = m, minor radius (along the horizontal axis) b=0.67 m and plasma elongation K 1.68.…”

“…The calculations are performed for the geometry of the T-15MD tokamak [35][36][37][38][39][40][41][42][43][44][45][46][47] now under construction in Kurchatov Institute. Its operation has been first announced to be in 2016 [40] (under the name Tokamak T-15 upgrade), then in 2018 at the first page in [42] and in 2019 at the end of the same paper [42], then again in 2019 [43], and currently it is shifted to the end of 2020 [47].…”

“…Its operation has been first announced to be in 2016 [40] (under the name Tokamak T-15 upgrade), then in 2018 at the first page in [42] and in 2019 at the end of the same paper [42], then again in 2019 [43], and currently it is shifted to the end of 2020 [47]. The project T-15MD has been also intermittently referred to as T-15 [36,38,41,44,45], T-15M [37], and T-15 Upgrade [39,40]. To avoid confusion, we have to explain that the same names have been attributed to another device T-15 built, tested and positioned among operating devices [48], though its target plasma operation has never been achieved.…”

“…The presently discussed T-15MD is an essentially different device despite Modified in MD (D=divertor) combined with the misleading 15 in the name. The abbreviation T-15MD was introduced in [35] and is officially accepted now [42,43,46,47], it covers everything described in [35][36][37][38][39][40][41][42][43][44][45][46][47].…”

“…Several scenarios for T-15MD have been discussed in[36][37][38][39]44]. Here we consider quasi-stationary stage of Ohmically heated discharge with expected T-15MD parameters.The pre-disruption plasma is described by the uniform plasma density n ψ is the poloidal magnetic flux, ax y is its value at the magnetic axis and bnd y is the flux at the plasma boundary, with on-axis values T T 1 the edge.…”