title: ÐÐ¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÑÐ¿ÐµÑÐ¸Ð°Ð»ÑÐ½ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð¾Ð² Ð¾ÑÑÑÐ²Ð° Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ-ÑÐµÐ°ÐºÑÐ¾ÑÐµ 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: Modeling of special detachment regimes for the ITER tokamak-reactor
Creators: name: ÐÐ¾Ð»ÐµÑÐ°ÐµÐ²Ð°, ÐÐ½Ð°ÑÑÐ°ÑÐ¸Ñ
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: 2021
Subjects: ÑÐ¸Ð·Ð¸ÐºÐ° Ð¿Ð»Ð°Ð·Ð¼Ñ
Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð°Ñ Ð¿Ð»Ð°Ð·Ð¼Ð°
ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ
ÑÐµÐ¶Ð¸Ð¼ Ð¾ÑÑÑÐ²Ð°
ÑÐ¸ÑÐ¸Ð½Ð° Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»Ð¾Ñ
plasma physics
edge plasma
numerical modeling
detachment
scrape-off-layer width

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð¾Ð¹ Ð¿Ð»Ð°Ð·Ð¼Ñ ÑÐ¾ÐºÐ°-Ð¼Ð°ÐºÐ°-ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐ¢Ð­Ð  ÐºÐ¾Ð´Ð¾Ð¼ SOLPS-ITER. Ð Ð½Ð°ÑÑÐ¾ÑÑÐµÐµ Ð²ÑÐµÐ¼Ñ Ð´Ð¾ Ð·Ð°Ð¿ÑÑÐºÐ° ÐÐ¢Ð­Ð  Ð½ÐµÐ¸Ð·Ð²ÐµÑÑÐ½Ð¾, ÐºÐ°ÐºÐ¾Ð¹ Ð² Ð½ÑÐ¼ Ð±ÑÐ´ÐµÑ ÑÐ¸ÑÐ¸Ð½Ð° Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»Ð¾Ñ (SOL). Ð¨Ð¸ÑÐ¸Ð½Ð° SOL Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÑÐµÑ Ð² ÑÐ¾Ð¼ ÑÐ¸ÑÐ»Ðµ Ð½Ð°Ð³ÑÑÐ·ÐºÑ Ð½Ð° Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ½ÑÐµ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ. ÐÑÐ»Ð¸ ÑÐ¸ÑÐ¸Ð½Ð° SOL Ð´Ð»Ñ ÐÐ¢Ð­Ð  Ð±ÑÐ´ÐµÑ Ð¾ÐºÐ¾Ð»Ð¾ Ð¼Ð¸Ð»Ð»Ð¸Ð¼ÐµÑÑÐ°, ÐºÐ°Ðº Ð¿ÑÐµÐ´ÑÐºÐ°Ð·ÑÐ²Ð°ÐµÑÑÑ Ð¸Ð· ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½ÑÑ ÑÐºÐµÐ¹Ð»Ð¸Ð½Ð³Ð¾Ð², ÑÐ¾ Ð¿ÑÐ¸ÑÐ¾Ð´ÑÑÐ°Ñ Ð½Ð° Ð¿Ð»Ð°ÑÑÐ¸Ð½Ñ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ° Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ Ð¼Ð¾Ð¶ÐµÑ Ð¿ÑÐµÐ²ÑÑÐ¸ÑÑ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÐ¹ Ð¿ÑÐµÐ´ÐµÐ». Ð¢Ð°ÐºÐ¶Ðµ Ð²Ð°Ð¶Ð½ÑÐ¼ Ð²Ð¾Ð¿ÑÐ¾ÑÐ¾Ð¼ ÑÐ²Ð»ÑÐµÑÑÑ Ð¼ÐµÑÐ°Ð½Ð¸Ð·Ð¼ ÑÐ¾ÑÐ¼Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»Ð¾Ñ Ð² ÑÐ»ÑÑÐ°Ðµ ÑÐ·ÐºÐ¾Ð³Ð¾ SOL Ð¸ Ð² ÑÐ»ÑÑÐ°Ðµ, ÐµÑÐ»Ð¸ ÑÐ¸ÑÐ¸Ð½Ð° SOL Ð´Ð»Ñ ÐÐ¢Ð­Ð  Ð±ÑÐ´ÐµÑ Ð¾ÐºÐ¾Ð»Ð¾ 3â4 Ð¼Ð¼, ÐºÐ°Ðº Ð¿ÑÐµÐ´ÑÐºÐ°Ð·ÑÐ²Ð°ÐµÑ ÐºÐ¸Ð½ÐµÑÐ¸ÑÐµÑÐºÐ¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ. Ð ÑÐ°Ð±Ð¾ÑÐµ Ð±ÑÐ»Ð¾ Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð´Ð»Ñ ÐÐ¢Ð­Ð  Ñ ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð½Ð¾Ð¹ ÑÐ¸ÑÐ¸Ð½Ð¾Ð¹ Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»Ð¾Ñ Ð·Ð° ÑÑÑÑ Ð¿Ð¾Ð½Ð¸Ð¶ÐµÐ½Ð¸Ñ Ð°Ð½Ð¾Ð¼Ð°Ð»ÑÐ½ÑÑ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¿ÐµÑÐµÐ½Ð¾ÑÐ°, Ð¾Ð´Ð½Ð°ÐºÐ¾ Ð² Ð½ÑÐ¼ Ð½Ðµ ÑÑÐ¸ÑÑÐ²Ð°Ð»Ð¸ÑÑ Ð´ÑÐµÐ¹ÑÐ¾Ð²ÑÐµ ÑÑÑÐµÐºÑÑ, ÐºÐ¾ÑÐ¾ÑÑÐµ Ð² ÑÐ»ÑÑÐ°Ðµ ÑÐ·ÐºÐ¾Ð³Ð¾ SOL Ð¼Ð¾Ð³ÑÑ Ð¸Ð³ÑÐ°ÑÑ ÑÑÑÐµÑÑÐ²ÐµÐ½Ð½ÑÑ ÑÐ¾Ð»Ñ. ÐÐ¾ÑÑÐ¾Ð¼Ñ ÑÐµÐ»ÑÐ¼Ð¸ Ð´Ð°Ð½Ð½Ð¾Ð¹ ÐÐÐ  ÑÐ²Ð»ÑÐµÑÑÑ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð¾Ð¹ Ð¿Ð»Ð°Ð·Ð¼Ñ ÐºÐ¾Ð´Ð¾Ð¼ SOLPS-ITER ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°-ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐ¢Ð­Ð  Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÐ¼Ð¸ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ°Ð¼Ð¸ Ð¿ÐµÑÐµÐ½Ð¾ÑÐ°, Ð¿Ð¾Ð·Ð²Ð¾Ð»ÑÑÑÐ¸Ð¼Ð¸ Ð¿Ð¾Ð»ÑÑÐ¸ÑÑ Ð²Ð°ÑÐ¸Ð°Ð½ÑÑ Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½Ð¾Ð¹ ÑÐ¸ÑÐ¸Ð½Ð¾Ð¹ Ð¾Ð±Ð´Ð¸ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»Ð¾Ñ, Ð° ÑÐ°ÐºÐ¶Ðµ Ð°Ð½Ð°Ð»Ð¸Ð· ÑÐ¸ÑÐ¸Ð½Ñ SOL, Ð¼ÐµÑÐ°Ð½Ð¸Ð·Ð¼Ð° ÑÐ¾ÑÐ¼Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ SOL Ð¸ ÑÐ¾Ð»Ð¸ Ð´ÑÐµÐ¹ÑÐ¾Ð²ÑÑ ÑÑÑÐµÐºÑÐ¾Ð² Ð´Ð»Ñ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð½ÑÑ ÑÐ°ÑÑÐµÑÐ¾Ð². Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ ÑÐ°Ð±Ð¾ÑÑ Ð¿Ð¾Ð»ÑÑÐµÐ½Ð¾, ÑÑÐ¾ Ð¿ÑÐ¸ ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð¸Ð¸ Ð°Ð½Ð¾Ð¼Ð°Ð»ÑÐ½ÑÑ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¿ÐµÑÐµÐ½Ð¾ÑÐ° Ð² SOL Ð² 4 ÑÐ°Ð·Ð° Ð¿Ð¾ ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ñ ÑÐ¾ Ð·Ð½Ð°ÑÐµÐ½Ð¸ÑÐ¼Ð¸, Ð¿ÑÐ¸Ð½ÑÑÑÐ¼Ð¸ Ð´Ð»Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÐÐ¢Ð­Ð , ÑÐ¸ÑÐ¸Ð½Ð° SOL Ð¿Ð¾ Ð¿Ð¾ÑÐ¾ÐºÑ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸ ÑÐ¼ÐµÐ½ÑÑÐ°ÐµÑÑÑ Ð´Ð¾ Ð·Ð½Ð°ÑÐµÐ½Ð¸Ñ 1.65 Ð¼Ð¼ Ð¸ ÑÑÑÐµÑÑÐ²ÐµÐ½Ð½ÑÐ¹ Ð²ÐºÐ»Ð°Ð´ Ð² Ð¿ÐµÑÐµÐ½Ð¾Ñ ÑÐ°ÑÑÐ¸Ñ Ð½Ð° Ð¼Ð°ÑÑÑÐ°Ð±Ð°Ñ ÑÐ¸ÑÐ¸Ð½Ñ SOL Ð²Ð½Ð¾ÑÐ¸Ñ Ð¿Ð¾ÑÐ¾Ðº, ÑÐ²ÑÐ·Ð°Ð½Ð½ÑÐ¹ Ñ Ð³ÑÐ°Ð´Ð¸ÐµÐ½ÑÐ½ÑÐ¼ Ð¼Ð°Ð³Ð½Ð¸ÑÐ½ÑÐ¼ Ð´ÑÐµÐ¹ÑÐ¾Ð¼, ÐºÐ¾Ð³Ð´Ð° Ð² ÑÐ»ÑÑÐ°Ðµ Â«ÑÑÐ°Ð½Ð´Ð°ÑÑÐ½ÑÑÂ» ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¿ÐµÑÐµÐ½Ð¾ÑÐ° ÑÐ¸ÑÐ¸Ð½Ð° SOL ÑÐ¾ÑÑÐ°Ð²Ð»ÑÐµÑ 3.43 Ð¼Ð¼ Ð¸ Ð¼Ð¾Ð¶ÐµÑ Ð±ÑÑÑ Ð´Ð¾ÑÑÐ¸Ð³Ð½ÑÑÐ° ÑÐ¾Ð»ÑÐºÐ¾ Ð¿Ð¾Ð´ Ð´ÐµÐ¹ÑÑÐ²Ð¸ÐµÐ¼ Ð°Ð½Ð¾Ð¼Ð°Ð»ÑÐ½Ð¾Ð³Ð¾ ÑÑÑÐ±ÑÐ»ÐµÐ½ÑÐ½Ð¾Ð³Ð¾ Ð¿ÐµÑÐµÐ½Ð¾ÑÐ°. Ð Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð½ÑÑ ÑÐ°ÑÑÑÑÐ°Ñ Ñ Ð½ÐµÐ¹ÑÑÐ°Ð»ÑÐ½ÑÐ¼ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸ÐµÐ¼ 7 ÐÐ° Ð² Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐµ Ð² ÑÐ»ÑÑÐ°Ðµ Â«ÑÐ·ÐºÐ¾Ð³Ð¾ SOLÂ» Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ Ð½Ð° Ð²Ð½ÐµÑÐ½ÐµÐ¹ Ð¿Ð»Ð°ÑÑÐ¸Ð½Ðµ Ð¿ÑÐµÐ²ÑÑÐ°ÐµÑ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÐ¹ Ð¿ÑÐµÐ´ÐµÐ» Ð² 10 ÐÐÑ/Ð¼Â² Ð¸ ÑÐ¾ÑÑÐ°Ð²Ð»ÑÐµÑ 11,4 ÐÐÑ/Ð¼Â². ÐÐ¾Ð»ÑÑÐµÐ½Ð½ÑÐµ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÑ Ð²Ð¾ÑÐ»Ð¸ Ð² ÑÐ°Ð±Ð¾ÑÑ Ð¸ Ð¿Ð¾Ð´ÑÐ²ÐµÑÐ¶Ð´Ð°ÑÑ Ð²ÑÐ²Ð¾Ð´, ÑÑÐ¾ ÑÑÑÐµÑÑÐ²ÑÐµÑ ÑÐ·ÐºÐ°Ñ Ð¾Ð±Ð»Ð°ÑÑÑ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð², Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÑ Ð´Ð»Ñ ÑÐ°Ð±Ð¾ÑÑ Ð±ÑÐ´ÑÑÐµÐ³Ð¾ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°-ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐ¢Ð­Ð , Ð½Ðµ Ð¿ÑÐ¸Ð²Ð¾Ð´ÑÑÐ°Ñ Ðº Ð¿ÑÐµÐ²ÑÑÐµÐ½Ð¸Ñ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÑ Ð½Ð°Ð³ÑÑÐ·Ð¾Ðº Ð½Ð° Ð¿Ð»Ð°ÑÑÐ¸Ð½Ð°Ñ Ð´Ð¸Ð²ÐµÑÑÐ¾ÑÐ°.
description: The given work is devoted to SOLPS-ITER modeling of edge plasma of the ITER (International Thermonuclear Experimental Reactor) tokamak-reactor. Be-fore the launch of ITER, the Scrape-off-layer (SOL) width is unknown. The SOL width determines the load on the divertor plates. The experimental scaling pre-dicts the SOL width for ITER is about a millimeter and such width can lead to exceeding the power flux at the divertor plates. Kinetic modeling predicts SOL width for ITER is about 3-4 mm. Another important issue is the mechanism of the SOL forming in the cases of a narrow SOL and predicted one. In, a simulation was made for ITER with a reduced SOL width due to decrease of anomalous transport coefficients in the SOL. Drift effects were not considered in that simulation, but they can be important in the narrow SOL case. The goals of this work are the SOLPS-ITER simulation of the edge plasma of the ITER toka-mak-reactor with different anomalous transport coefficients, leading to different SOL widths cases, SOL width and the mechanism of SOL formation analysis and the role of drift effects analysis for these cases. This work shows that the SOL power flux width is 1.65 mm when the anomalous transport coefficients in SOL decrease by 4 times. In this case flux associated with magnetic drift make a significant contribution to the particles transport. In the case of âstandardâ transfer coefficients for ITER modeling, the SOL width is 3.43 mm and can be achieved only under the anomalous turbulent transport. In the simulation of narrow SOL with a neutral pressure 7 Pa at the divertor region, the power load to the outer divertor plate is 11.4 MW / mÂ² that exceeds the limit of 10 MW / mÂ². The obtained results were included in work and confirm the conclusion that there is a narrow operation window for the future ITER toka-mak-reactor, which does not lead to exceeding the permissible loads on the di-vertor plates.