title: ÐÐ¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐµÐ¶Ð¸Ð¼Ð¾Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° ÐºÐ¾Ð´Ð¾Ð¼ SOLPS-ITER
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 dynamic modes in a tokamak with the SOLPS-ITER code
Creators: name: Ð¨Ð°Ð½Ð´Ð¸Ð½, ÐÐ°Ð»ÐµÑÐ¸Ð¹
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
ÑÐ¾ÐºÐ°Ð¼Ð°Ðº
ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ
Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ
Ð´Ð¸Ð²ÐµÑÑÐ¾Ñ
Ð´ÐµÑÐ°ÑÐ¼ÐµÐ½Ñ
Ð²ÑÑÐ¾ÐºÐ¸Ð¹ ÑÐµÑÐ¸ÐºÐ»Ð¸Ð½Ð³
SOLPS-ITER
Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐµÐ¶Ð¸Ð¼
SSDOs
CFETR
ASDEX Upgrade
JET
plasma physics
tokamak
numerical simulation
divertor
detachment
high recycling
dynamic regime

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐµÐ¶Ð¸Ð¼Ð¾Ð² ÑÐ°Ð±Ð¾ÑÑ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° ÐºÐ¾Ð´Ð¾Ð¼ SOLPS-ITER. ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ ÑÐ°ÐºÐ¸Ñ ÑÐµÐ¶Ð¸Ð¼Ð¾Ð² Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾, Ð¿Ð¾ÑÐºÐ¾Ð»ÑÐºÑ Ð² ÑÐ¾Ð´Ðµ Ð½ÐµÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½ÑÑ ÑÐ°Ð·ÑÑÐ´Ð¾Ð² ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ñ Ð¿Ð»Ð°Ð·Ð¼Ñ Ð¿ÑÐµÑÐµÑÐ¿ÐµÐ²Ð°ÐµÑ ÑÑÑÐµÑÑÐ²ÐµÐ½Ð½ÑÐµ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ, Ð° ÑÐ°ÐºÐ¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ ÐºÐ°Ðº ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ° Ð¸ Ð¿Ð¾ÑÐ¾ÐºÐ¸ ÑÐµÐ¿Ð»Ð°, Ð¿ÑÐ¸ÑÐ¾Ð´ÑÑÐ¸Ðµ Ð½Ð° Ð¼Ð°ÑÐµÑÐ¸Ð°Ð»ÑÐ½ÑÐµ Ð¿Ð¾Ð²ÐµÑÑÐ½Ð¾ÑÑÐ¸ ÐºÐ°Ð¼ÐµÑÑ, Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾ Ð¾ÑÑÐ»ÐµÐ¶Ð¸Ð²Ð°ÑÑ Ð½Ð° Ð¿ÑÐ¾ÑÑÐ¶ÐµÐ½Ð¸Ð¸ Ð²ÑÐµÐ³Ð¾ ÑÐ°Ð·ÑÑÐ´Ð°, Ð´Ð°Ð¶Ðµ ÐµÑÐ»Ð¸ Ð¿Ð¾ÑÐ»ÐµÐ´Ð½Ð¸Ð¹ Ð¿ÐµÑÐµÑÐ¾Ð´Ð¸Ñ Ðº ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð¼Ñ ÑÐµÐ¶Ð¸Ð¼Ñ. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð¾ÑÐ´ÐµÐ»ÑÐ½Ð¾ Ð¸ÑÑÐ»ÐµÐ´ÑÐµÑÑÑ ÐºÐ»Ð°ÑÑ ÑÐµÑÐµÐ½Ð¸Ð¹, ÐºÐ¾ÑÐ¾ÑÑÐ¹ Ð½Ð¾ÑÐ¸Ñ ÐºÐ¾Ð»ÐµÐ±Ð°ÑÐµÐ»ÑÐ½ÑÐ¹ ÑÐ°ÑÐ°ÐºÑÐµÑ. ÐÐ»Ñ Ð½ÐµÐ³Ð¾ Ð¿ÑÐ°Ð²Ð¸Ð»ÑÐ½Ð¾Ðµ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¾Ðµ Ð¾Ð¿Ð¸ÑÐ°Ð½Ð¸Ðµ ÑÐ²Ð»ÑÐµÑÑÑ ÐµÐ´Ð¸Ð½ÑÑÐ²ÐµÐ½Ð½Ð¾ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½ÑÐ¼. Ð¢Ð°ÐºÐ¾Ð¹ ÑÐµÐ¶Ð¸Ð¼ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Ð½Ð°Ð±Ð»ÑÐ´Ð°Ð»ÑÑ Ð² ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ñ Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°Ñ ASDEX Upgrade Ð¸ JET. ÐÐ¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¸Ð»Ð¾ÑÑ Ð²ÐµÑÑÐ¸ÐµÐ¹ ÐºÐ¾Ð´Ð° 3.0.6, ÐºÐ¾ÑÐ¾ÑÐ°Ñ ÑÐ°Ð½ÐµÐµ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð»Ð°ÑÑ Ð´Ð»Ñ Ð¿Ð¾Ð¸ÑÐºÐ° ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð¹ ÐºÐ¾Ð½ÑÐ¸Ð³ÑÑÐ°ÑÐ¸Ð¸ Ð¿ÑÐ¸ÑÑÐµÐ½Ð¾ÑÐ½Ð¾Ð¹ Ð¿Ð»Ð°Ð·Ð¼Ñ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°. Ð¢ÐµÐ¼ Ð½Ðµ Ð¼ÐµÐ½ÐµÐµ, ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð°Ñ ÑÑÐµÐ¼Ð° Ð² Ð½ÐµÐ¼ ÑÐµÐ°Ð»Ð¸Ð·Ð¾Ð²Ð°Ð½Ð° ÑÐ°Ðº, ÑÑÐ¾ Ð½Ð° ÐºÐ°Ð¶Ð´Ð¾Ð¹ Ð¸ÑÐµÑÐ°ÑÐ¸Ð¸ Ð¸ÑÐµÑÑÑ Ð¿ÑÐ¸ÑÐ°ÑÐµÐ½Ð¸Ðµ Ð¸ÑÐºÐ¾Ð¼ÑÑ Ð²ÐµÐ»Ð¸ÑÐ¸Ð½ Ð¿Ð¾ Ð²ÑÐµÐ¼ÐµÐ½Ð¸, ÑÐ¾ ÐµÑÑÑ ÐºÐ¾Ð´ Ð² Ð¿ÑÐ¸Ð½ÑÐ¸Ð¿Ðµ Ð´Ð¾Ð»Ð¶ÐµÐ½ Ð¿Ð¾Ð·Ð²Ð¾Ð»ÑÑÑ ÑÐ°ÑÑÑÐ¸ÑÑÐ²Ð°ÑÑ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ðµ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ, Ð¿ÑÐ¸ ÑÑÐ»Ð¾Ð²Ð¸Ð¸ Ð´Ð¾ÑÑÐ°ÑÐ¾ÑÐ½Ð¾ Ð¼Ð°Ð»Ð¾Ð³Ð¾ ÑÐ°Ð³Ð° Ð¿Ð¾ Ð²ÑÐµÐ¼ÐµÐ½Ð¸. Ð ÑÐµÑÐ¸Ð¸ ÑÐµÑÑÐ¾Ð²ÑÑ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐ°ÑÑÐµÑÐ¾Ð², Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð½ÑÑ Ð² Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ, Ð² Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸Ð¸ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° CFETR Ð±ÑÐ»Ð¸ Ð²ÑÑÐ²Ð»ÐµÐ½Ñ ÑÐµÑÐµÐ½Ð¸Ñ ÐºÐ¾Ð»ÐµÐ±Ð°ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ ÑÐ¸Ð¿Ð°. ÐÑÐ¸ Ð±Ð¾Ð»ÐµÐµ Ð´ÐµÑÐ°Ð»ÑÐ½Ð¾Ð¼ Ð°Ð½Ð°Ð»Ð¸Ð·Ðµ Ð¿ÑÐ¾ÑÐ¸Ð»ÐµÐ¹ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² Ð¿Ð»Ð°Ð·Ð¼Ñ Ð±ÑÐ»Ð¾ Ð¾Ð±Ð½Ð°ÑÑÐ¶ÐµÐ½Ð¾, ÑÑÐ¾ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð°Ñ ÑÑÐµÐ¼Ð° ÑÐµÐ°Ð»Ð¸Ð·Ð¾Ð²Ð°Ð½Ð½Ð°Ñ Ð² Ð²ÐµÑÑÐ¸Ð¸ ÐºÐ¾Ð´Ð° SOLPS-ITER 3.0.6, Ð´Ð°ÑÑÐ°Ñ ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸ Ð¿ÑÐ°Ð²Ð¸Ð»ÑÐ½ÑÐµ ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½ÑÐµ ÑÐµÑÐµÐ½Ð¸Ñ, Ð¿ÑÐ¸Ð²Ð¾Ð´Ð¸Ñ Ðº ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾ Ð½ÐµÐ²ÐµÑÐ½ÑÐ¼ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼ Ð¿ÑÐ¸ Ð¿Ð¾Ð¿ÑÑÐºÐµ Ð¿ÑÐ¸Ð¼ÐµÐ½Ð¸ÑÑ ÐµÐµ Ðº Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¾Ð¹ Ð·Ð°Ð´Ð°ÑÐµ.
description: This work is devoted to model of dynamic operation modes of a tokamak using the SOLPS-ITER code. The study of such modes is necessary, since during non- stationary discharges the configuration of a plasma undergoes significant changes. Magnitudes of such characteristics as a temperature and heat fluxes arriving at the material surfaces of the tokamak chamber must be monitored throughout the entire discharge, even if the latter tends to a stationary one. In this work we specially investigate the class of solutions, which has an oscillatory nature. In such case a correct dynamic description is the only possible one. Such operation regime was previously observed in experiments on the ASDEX Upgrade and JET tokamaks. The simulation was carried out with code version 3.0.6, which was previously used to search for the stationary configuration of the plasma. Nevertheless, the numerical scheme in this code at each iteration calculate the time variation of the sought-for values. So, in principle, this version of the code can calculate dynamic changes, if the time step is sufficiently small. In a series of the test simulations carried out in this work, oscillations were revealed in the geometry of the CFETR tokamak. Detailed analysis of the profiles of plasma parameters revealed that the numerical scheme implemented in version 3.0.6 of the SOLPS-ITER code, which gives physically correct stationary solutions, leads to numerically incorrect results when we try to apply it to a dynamic problem.