title: ÐÐ¿ÑÐ¸Ð¼Ð¸Ð·Ð°ÑÐ¸Ñ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½Ð¾Ð¹ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸ Ð´Ð»Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Ð¢Ð Ð¢
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð±Ð°ÐºÐ°Ð»Ð°Ð²ÑÐ°
titleType: Subtitle
title: Optimization of the divertor configuration for TRT tokamak
Creators: name: ÐÑÐ´ÑÐµÐ²Ð°ÑÑÑ, ÐÐ°Ð²ÐµÐ»
Publisher: name: Ð¡Ð°Ð½ÐºÑ-ÐÐµÑÐµÑÐ±ÑÑÐ³ÑÐºÐ¸Ð¹ Ð¿Ð¾Ð»Ð¸ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ½Ð¸Ð²ÐµÑÑÐ¸ÑÐµÑ ÐÐµÑÑÐ° ÐÐµÐ»Ð¸ÐºÐ¾Ð³Ð¾
Year: 2023
Subjects: Ð¿Ð»Ð°Ð·Ð¼Ð°
ÑÐ¾ÐºÐ°Ð¼Ð°Ðº
SOLPS-ITER
Ð´Ð¸Ð²ÐµÑÑÐ¾Ñ
Ð¢Ð Ð¢
plasma
tokamak
divertor
TRT

description: ÐÐ´Ð½Ð¾Ð¹ Ð¸Ð· Ð¾ÑÐ½Ð¾Ð²Ð½ÑÑ Ð·Ð°Ð´Ð°Ñ Ð² Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ð¸ ÑÐµÑÐ¼Ð¾ÑÐ´ÐµÑÐ½ÑÑ ÑÑÑÐ°Ð½Ð¾Ð²Ð¾Ðº Ð½Ð° Ð¾ÑÐ½Ð¾Ð²Ðµ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° ÑÐ²Ð»ÑÐµÑÑÑ ÑÐ½Ð¸Ð¶ÐµÐ½Ð¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð²ÑÑ Ð½Ð°Ð³ÑÑÐ·Ð¾Ðº Ð½Ð° ÑÑÐµÐ½ÐºÐ¸ Ð²Ð°ÐºÑÑÐ¼Ð½Ð¾Ð¹ ÐºÐ°Ð¼ÐµÑÑ. ÐÐ° ÑÐµÐºÑÑÐ¸Ð¹ Ð¼Ð¾Ð¼ÐµÐ½Ñ ÑÑÐ¾ Ð´ÐµÐ»Ð°ÐµÑÑÑ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½Ð¾Ð¹ Ð¼Ð°Ð³Ð½Ð¸ÑÐ½Ð¾Ð¹ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸: Ð¿Ð¾ÑÐ¾ÐºÐ¸ ÑÐµÐ¿Ð»Ð° Ð²ÑÑÐ¾Ð´ÑÑ Ð¸Ð· Ð·Ð¾Ð½Ñ ÑÐ´ÐµÑÐ¶Ð°Ð½Ð¸Ñ Ð¸ ÑÐ¿ÑÑÐºÐ°ÑÑÑÑ Ð¿Ð¾Ð»Ð¾Ð¸Ð´Ð°Ð»ÑÐ½Ð¾ Ð½Ð° Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½ÑÐµ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ. ÐÐ½Ð¸ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ñ Ð½Ð° Ð±Ð¾Ð»ÑÑÐ¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐµ Ð½Ð°Ð³ÑÑÐ·ÐºÐ¸ Ð¸ Ð¾ÑÐ»Ð°Ð¶Ð´Ð°ÑÑÑÑ Ð´Ð¾Ð¿Ð¾Ð»Ð½Ð¸ÑÐµÐ»ÑÐ½Ð¾. ÐÐ¾ Ð¸Ñ Ð¾Ð¿ÐµÑÐ°ÑÐ¸Ð¾Ð½Ð½ÑÐµ Ð¿ÑÐµÐ´ÐµÐ»Ñ ÑÐ¾Ð¶Ðµ ÐºÐ¾Ð½ÐµÑÐ½Ñ, Ð¸, Ðº Ð¿ÑÐ¸Ð¼ÐµÑÑ, Ð´Ð»Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° ITER ÑÑÐ¾ q = 10 ÐÐ/Ð¼2 Ð² ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð¼ ÑÐµÐ¶Ð¸Ð¼Ðµ ÑÐ°Ð±Ð¾ÑÑ, Ð½Ðµ ÑÑÐ¸ÑÑÐ²Ð°Ñ Ð¿ÐµÑÐµÑÐ¾Ð´Ð½ÑÑ Ð¿ÑÐ¾ÑÐµÑÑÐ¾Ð². ÐÐ»Ñ ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð¸Ñ ÑÐµÐ¿Ð»Ð¾Ð²ÑÑ Ð½Ð°Ð³ÑÑÐ·Ð¾Ðº ÑÐµÐ¹ÑÐ°Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·ÑÐµÑÑÑ Ð½Ð°Ð¿ÑÑÐº Ð¿ÐµÑÐµÐ¸Ð·Ð»ÑÑÐ°ÑÑÐµÐ¹ Ð¿ÑÐ¸Ð¼ÐµÑÐ¸ (Ð½ÐµÐ¾Ð½, Ð°Ð·Ð¾Ñ, Ð°ÑÐ³Ð¾Ð½), Ð° ÑÐ°Ðº Ð¶Ðµ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÐµ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½ÑÐµ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸: SuperâX Divertor, X Divertor Ð¸ Ð¼Ð½Ð¾Ð³Ð¸Ðµ Ð´ÑÑÐ³Ð¸Ðµ. ÐÐ½Ð¾Ð³Ð¾Ð¾Ð±ÐµÑÐ°ÑÑÐµÐ¹ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸ÐµÐ¹ ÑÐ²Ð»ÑÐµÑÑÑ Â«ÑÐ³Ð»Ð¾Ð²Ð°ÑÂ». ÐÐ½Ð° Ð±ÑÐ»Ð° ÑÑÐ¿ÐµÑÐ½Ð¾ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð° Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ EAST Ð¿Ð¾ÑÐ»Ðµ Ð¿ÑÐµÐ´Ð²Ð°ÑÐ¸ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÐºÐ¾Ð´Ð¾Ð¼ SOLPS-ITER. Ð ÑÐ¾ Ð¶Ðµ Ð²ÑÐµÐ¼Ñ Ð½Ðµ Ð¸Ð·Ð²ÐµÑÑÐ½Ð¾, Ð±ÑÐ´ÐµÑ Ð»Ð¸ Ð¾Ð½Ð° ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð° Ð½Ð° Ð´ÑÑÐ³Ð¸Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°Ñ, ÑÐ°ÐºÐ¸Ñ ÐºÐ°Ðº TRT. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ñ ÑÑÐ¸ Ð¾Ð¿ÐµÑÐ°ÑÐ¸Ð¾Ð½Ð½ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð° Â«ÑÐ³Ð»Ð¾Ð²Ð¾Ð³Ð¾Â» Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ° Ð´Ð»Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Ð¢Ð Ð¢, Ð° Ð¸Ð¼ÐµÐ½Ð½Ð¾ Ð¿Ð¾Ð¿Ð°Ð´Ð°Ð½Ð¸Ðµ ÑÐµÐ¿Ð°ÑÐ°ÑÑÐ¸ÑÑ Ð² Ð²ÐµÑÑÐ½ÑÑ, Ð½Ð¸Ð¶Ð½ÑÑ Ð¸ Â«ÑÐ³Ð»Ð¾Ð²ÑÑÂ» ÑÐ°ÑÑÐ¸ Ð¼Ð¸ÑÐµÐ½Ð¸. ÐÐ¾Ð»ÑÑÐµÐ½Ñ Ð´Ð°Ð½Ð½ÑÐµ Ð¾ Ð¿Ð»Ð¾ÑÐ½Ð¾ÑÑÐ¸ Ð¿Ð¾ÑÐ¾ÐºÐ° ÑÐ½ÐµÑÐ³Ð¸Ð¸ Ð½Ð° Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ, Ð¾ÑÐµÐ½ÐºÐ¸ Ð´Ð»Ñ ÑÑÐ»Ð¾Ð²Ð¸Ð¹ ÑÐ¾ÑÐ¼Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð³Ð°Ð·Ð¾Ð²Ð¾Ð¹ Ð¼Ð¸ÑÐµÐ½Ð¸ Ð½Ð° Ð²Ð½ÐµÑÐ½ÐµÐ¹ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ðµ. ÐÐ°Ð±Ð»ÑÐ´Ð°ÐµÑÑÑ ÑÐµÐ¶Ð¸Ð¼ Ð¾ÑÑÑÐ²Ð° Ð´Ð»Ñ Ð³Ð¾ÑÐ¸Ð·Ð¾Ð½ÑÐ°Ð»ÑÐ½Ð¾Ð¹ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ, Ð´Ð»Ñ Ð´Ð²ÑÑ Ð´ÑÑÐ³Ð¸Ñ ÑÑÐ¾Ñ ÑÐµÐ¶Ð¸Ð¼ ÑÐ¼ÐµÐ½ÑÐµÑÑÑ Ð½Ð° ÑÐ°ÑÑÐ¸ÑÐ½ÑÐ¹ Ð¾ÑÑÑÐ². ÐÐ»Ð¾ÑÐ½Ð¾ÑÑÐ¸ Ð¿Ð¾ÑÐ¾ÐºÐ° ÑÐ½ÐµÑÐ³Ð¸Ð¸ Ð² Ð³Ð¾ÑÐ¸Ð·Ð¾Ð½ÑÐ°Ð»ÑÐ½Ð¾Ð¹ Ð¸ ÑÐ³Ð»Ð¾Ð²Ð¾Ð¹ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸ Ð½Ðµ Ð¿ÑÐµÐ²ÑÑÐ°ÑÑ 10 ÐÐ/Ð¼2, ÑÑÐ¾ Ð´ÐµÐ»Ð°ÐµÑ ÑÐ°ÐºÐ¸Ðµ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½ÑÐ¼Ð¸ Ð´Ð»Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Ð¢Ð Ð¢. ÐÐµÑÑÐ¸ÐºÐ°Ð»ÑÐ½Ð°Ñ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ñ ÑÐ²Ð»ÑÐµÑÑÑ Ð½ÐµÐ¿ÑÐ¸ÐµÐ¼Ð»ÐµÐ¼Ð¾Ð¹ Ð¸Ð·-Ð·Ð° Ð²ÑÑÐ¾ÐºÐ¾Ð³Ð¾ ÑÐ°ÑÐ¿ÑÐ»ÐµÐ½Ð¸Ñ Ð¸ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½Ð¾Ð³Ð¾ ÑÐ°ÑÐ¿Ð»Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð²Ð¾Ð»ÑÑÑÐ°Ð¼Ð°.
description: One of the main goals in the construction of a tokamak is the reduction of thermal loads on the walls of the vacuum chamber. Currently, this is done using a divertor magnetic configuration: heat flows out of the confinement zone and descend poloidally onto the divertor plates. They are designed for high thermal loads and are additionally cooled. But their limits are also finite, and, for example, for the ITER tokamak it is q = 10 MW/m2 in the stationary mode of operation, not taking into account transients. To reduce thermal loads, impurities seeding (neon, nitrogen, argon) is now used, as well as various divertor configurations, such as SuperâX Divertor, X Divertor and many others. A promising configuration is the Â«cornerÂ» one, which has already been used on the EAST tokamak and is successfully modeled by the SOLPS-ITER code. At the same time, it is not known whether it will be effective on other tokamaks, such as TRT. In this work, three operating modes of the Â«cornerÂ» divertor for the TRT tokamak reactor are investigated, namely, the separatrix hitting the upper, lower, and âcornerâ targets. Data on the density of the energy flux to the plates and estimates of the formation of a gas target for the outer plate are obtained. A detachment mode is observed for a horizontal plate, for the other two this mode is replaced by a semi-detachment. The energy flux densities for the horizontal and corner configurations do not exceed 10 MW/m2, which makes such configurations possible for the TRT tokamak. The vertical configuration is unacceptable due to the high sputtering and possible melting of the tungsten.