title: ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð²Ð»Ð¸ÑÐ½Ð¸Ñ ÑÐ¾ÑÐ¾Ð¸Ð´Ð°Ð»ÑÐ½Ð¾Ð³Ð¾ Ð¸Ð½Ð´ÑÐºÑÐ¸Ð²Ð½Ð¾Ð³Ð¾ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¿Ð¾Ð»Ñ Ð½Ð° ÑÐ¾ÐºÐ¸ Ð² SOL Ð² Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸Ð¸ ÐÐ¢Ð­Ð
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: Investigation of the influence of a toroidal inductive electric field on currents in SOL within the ITER geometry
Creators: name: Ð¨Ð¸ÑÐ¾Ð±Ð¾ÐºÐ¾Ð², ÐÐ½Ð´ÑÐµÐ¹
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: ÑÐµÑÐ¼Ð¾ÑÐ´ÐµÑÐ½ÑÐ¹ ÑÐ¸Ð½ÑÐµÐ·
ÑÐ¾ÐºÐ°Ð¼Ð°Ðº
Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð°Ñ Ð¿Ð»Ð°Ð·Ð¼Ð°
ÐÐ¢Ð­Ð
Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½ÑÐ¹ ÑÐ»Ð¾Ð¹
ÑÑÑÐ² ÑÐ¾ÐºÐ°
Ð¸Ð½Ð´ÑÐºÑÐ¸Ð²Ð½Ð¾Ðµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ðµ Ð¿Ð¾Ð»Ðµ
Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ðµ Ð¾Ð±Ñ Ð¾Ð´Ð°
thermonuclear fusion
tokamak
plasma edge
ITER
scrape-off layer
current quench
loop voltage
induced electric field

description: Ð Ð±ÑÐ´ÑÑÐµÐ¼ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ ÐÐ¢Ð­Ð  Ð½Ð° ÑÑÐ°Ð´Ð¸Ð¸ ÑÑÑÐ²Ð° ÑÐ¾ÐºÐ° Ð¸Ð·-Ð·Ð° ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð¸Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ Ð¿Ð»Ð°Ð·Ð¼Ñ Ð¸ Ð¿Ð¾Ð²ÑÑÐµÐ½Ð¸Ñ ÐµÑ ÑÐ¾Ð¿ÑÐ¾ÑÐ¸Ð²Ð»ÐµÐ½Ð¸Ñ, Ð²ÐµÐ´ÑÑÐ¸Ñ Ðº ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð¸Ñ Ð¿Ð¾Ð»Ð¾Ð¸Ð´Ð°Ð»ÑÐ½Ð¾Ð³Ð¾ Ð¼Ð°Ð³Ð½Ð¸ÑÐ½Ð¾Ð³Ð¾ Ð¿Ð¾ÑÐ¾ÐºÐ°, Ð² ÑÐ¸Ð»Ñ Ð·Ð°ÐºÐ¾Ð½Ð° Ð¤Ð°ÑÐ°Ð´ÐµÑ Ð¼Ð¾Ð¶ÐµÑ Ð¿Ð¾ÑÐ²Ð»ÑÑÑÑÑ ÑÐ¾ÑÐ¾Ð¸Ð´Ð°Ð»ÑÐ½Ð¾Ðµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ðµ Ð¿Ð¾Ð»Ðµ Ð¸Ð½Ð´ÑÐºÑÐ¸Ð¾Ð½Ð½Ð¾Ð³Ð¾ ÑÐ¸Ð¿Ð°, Ð¾Ð±ÐµÑÐ¿ÐµÑÐ¸Ð²Ð°ÐµÐ¼Ð¾Ðµ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸ÐµÐ¼ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð²Ð¿Ð»Ð¾ÑÑ Ð´Ð¾ 1 ÐºÐ. ÐÐ°Ð½Ð½Ð¾Ðµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ðµ Ð¿Ð¾Ð»Ðµ Ð¼Ð¾Ð¶ÐµÑ Ð¿ÑÐ¸Ð²Ð¾Ð´Ð¸ÑÑ Ðº Ð·Ð½Ð°ÑÐ¸ÑÐµÐ»ÑÐ½Ð¾Ð¼Ñ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð¿ÑÐ¾ÑÐ¸Ð»ÐµÐ¹ ÑÐ¾ÐºÐ¾Ð², ÑÐµÐºÑÑÐ¸Ñ Ð² Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð¾Ð¹ Ð¾Ð±Ð»Ð°ÑÑÐ¸ Ð¿Ð»Ð°Ð·Ð¼Ñ, Ð½Ð°Ð·ÑÐ²Ð°ÐµÐ¼Ð¾Ð¹ Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½ÑÐ¼ ÑÐ»Ð¾ÐµÐ¼ (Scrape-Off Layer - SOL), Ð¸ Ð½Ð° Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ°. ÐÐ·Ð¼ÐµÐ½ÐµÐ½Ð¸Ðµ ÑÐ¾ÐºÐ¾Ð², ÑÐµÐºÑÑÐ¸Ñ Ð½Ð° Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ, Ð¼Ð¾Ð¶ÐµÑ Ð¿ÑÐ¸Ð²ÐµÑÑÐ¸ Ð¸ Ðº Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ ÑÐµÐ¿Ð»Ð¾Ð²ÑÑ Ð½Ð°Ð³ÑÑÐ·Ð¾Ðº, ÐºÐ¾ÑÐ¾ÑÑÐµ, Ð±ÑÐ´ÑÑÐ¸ ÑÐ»Ð¸ÑÐºÐ¾Ð¼ Ð²ÑÑÐ¾ÐºÐ¸Ð¼Ð¸, Ð¼Ð¾Ð³ÑÑ Ð¿ÑÐ¸Ð²ÐµÑÑÐ¸, Ð½Ð°Ð¿ÑÐ¸Ð¼ÐµÑ, Ðº ÑÐ°ÑÐ¿Ð»Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¿Ð»Ð°ÑÑÐ¸Ð½, ÑÐ°Ðº ÐºÐ°Ðº Ð¼Ð°ÐºÑÐ¸Ð¼Ð°Ð»ÑÐ½Ð¾ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼Ð°Ñ Ð¿Ð»Ð¾ÑÐ½Ð¾ÑÑÑ Ð¿Ð¾ÑÐ¾ÐºÐ° ÑÐ½ÐµÑÐ³Ð¸Ð¸ Ð½Ð° Ð½Ð¸Ñ Ð² ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð¼ ÑÐµÐ¶Ð¸Ð¼Ðµ ÑÐ°Ð±Ð¾ÑÑ ÐÐ¢Ð­Ð  Ð½Ðµ Ð´Ð¾Ð»Ð¶Ð½Ð° Ð¿ÑÐµÐ²ÑÑÐ°ÑÑ 10 ÐÐÑ/Ð¼2. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð¿ÑÐµÐ´Ð»Ð°Ð³Ð°ÐµÑÑÑ Ð¿ÑÐ¾ÑÑÐ°Ñ Ð°Ð½Ð°Ð»Ð¸ÑÐ¸ÑÐµÑÐºÐ°Ñ Ð¼Ð¾Ð´ÐµÐ»Ñ Ð¿Ð¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ Ð¿ÑÐ¾ÑÐ¸Ð»ÐµÐ¹ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¿Ð¾ÑÐµÐ½ÑÐ¸Ð°Ð»Ð° Ð¸ ÑÐ¾ÐºÐ¾Ð², ÑÐµÐºÑÑÐ¸Ñ Ð² SOL Ð¸ Ð½Ð° Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½ÑÐµ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ, Ð¿ÑÐ¸ Ð¿Ð¾ÑÐ²Ð»ÐµÐ½Ð¸Ð¸ Ð´Ð¾Ð¿Ð¾Ð»Ð½Ð¸ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð² Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸Ð¸ ÐÐ¢Ð­Ð . Ð¡ Ð¿Ð¾Ð¼Ð¾ÑÑÑ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ð³Ð¾ ÐºÐ¾Ð´Ð° SOLPS-ITER 3.0.8 Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÐÐ¢Ð­Ð  Ñ ÑÐ¸ÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð½ÑÐ¼Ð¸ Ð¿ÑÐ¾ÑÐ¸Ð»ÑÐ¼Ð¸ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑ Ð¸ ÐºÐ¾Ð½ÑÐµÐ½ÑÑÐ°ÑÐ¸Ð¹ Ð¿ÑÐ¸ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸ÑÑ Ð¾Ð±ÑÐ¾Ð´Ð°, Ð¿Ð¾Ð·Ð²Ð¾Ð»ÑÑÑÐ¸Ñ Ð¿Ð¾Ð»ÑÑÐ¸ÑÑ Ð½Ð°ÑÑÑÐµÐ½Ð¸Ðµ Ð²Ð¾Ð»ÑÑÐ°Ð¼Ð¿ÐµÑÐ½Ð¾Ð¹ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ (ÐÐÐ¥) SOL, Ð° ÑÐ°ÐºÐ¶Ðµ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÑ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐ°Ð¼Ð¾ÑÐ¾Ð³Ð»Ð°ÑÐ¾Ð²Ð°Ð½Ð½Ð¾Ð³Ð¾ ÑÐ°ÑÑÑÑÐ° Ð¾Ð´Ð½Ð¾Ð³Ð¾ Ð¸Ð· Ð±Ð°Ð·Ð¾Ð²ÑÑ Ð²Ð°ÑÐ¸Ð°Ð½ÑÐ¾Ð² ÐÐ¢Ð­Ð .
description: In the future ITER tokamak, at the current quench stage, due to a decrease in the plasma temperature and an increase in its resistivity, leading to a decrease in the poloidal magnetic flux, due to Faradayâs law, a toroidal electric field of the induction type may arise, provided by a loop voltage of up to 1 kV. This electric field can lead to a significant change in the profiles of currents flowing in the near-wall region of the plasma, called the Scrape-Off Layer (SOL), and on the divertor plates. A change in the currents flowing to the plates can also lead to a change in the heat loads, which, being too high, can lead, for example, to the melting of the plates, since the maximum allowable heat flux density on them in the steady-state mode of ITER operation should not exceed 10 MW/m2. In this paper, we propose a simple analytical model for the behavior of the profiles of the electrostatic potential and currents flowing in the SOL and on the divertor plates within the ITER geometry when an additional loop voltage appears. Using the numerical code SOLPS-ITER 3.0.8, ITER simulation data were obtained with fixed temperature and density profiles at various loop voltages, which make it possible to obtain saturation of the current-voltage characteristic (IâV curve) of the SOL, as well as the results of simulation of a self-consistent calculation of one of the basic ITER variants.