title: Ð§Ð¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð³ÐµÐ½ÐµÑÐ°ÑÐ¸Ð¸ ÑÐ¾ÐºÐ° ÑÐ²Ð»ÐµÑÐµÐ½Ð¸Ñ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð²Ð¾Ð»Ð½ Ð¿ÑÐ¾Ð¼ÐµÐ¶ÑÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ°ÑÑÐ¾ÑÐ½Ð¾Ð³Ð¾ Ð´Ð¸Ð°Ð¿Ð°Ð·Ð¾Ð½Ð° Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ Ð¤Ð¢-2
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: Numerical modeling of generation current drive using waves of the intermediate frequency range in the FT-2 tokamak
Creators: name: ÐÐ¾Ð²Ð¸ÐºÐ¾Ð², ÐÐ¼Ð¸ÑÑ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: 2024
Subjects: Ð¿Ð»Ð°Ð·Ð¼Ð°
ÑÐ¾ÐºÐ°Ð¼Ð°Ðº
Ð½Ð¸Ð¶Ð½ÐµÐ³Ð¸Ð±ÑÐ¸Ð´Ð½ÑÐ¹ Ð½Ð°Ð³ÑÐµÐ²
ÑÐ¾Ðº ÑÐ²Ð»ÐµÑÐµÐ½Ð¸Ñ
ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÑ
ÐºÐ¾ÑÑÐµ Ð»ÐµÐ½Ð³Ð¼ÑÑÐ¾Ð²ÑÐºÐ¸Ðµ Ð²Ð¾Ð»Ð½Ñ
plasma
tokamak
low-hybrid heating
current drive
efficiency
intermediate waves

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° ÐºÐ¾Ð¼Ð¿Ð»ÐµÐºÑÐ½Ð¾Ð¼Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ¾Ð² Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ Â«Ð¤Ð¢-2Â», ÑÑÐ¸ÑÑÐ²Ð°ÑÑÐ¸Ðµ ÐºÐ°Ðº ÑÐ²Ð¾Ð»ÑÑÐ¸Ñ Ð³Ð»Ð°Ð²Ð½ÑÑ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ°, ÑÐ°Ðº Ð¸ Ð¸Ñ ÑÐ°Ð´Ð¸Ð°Ð»ÑÐ½ÑÐµ Ð¿ÑÐ¾ÑÐ¸Ð»Ð¸. Ð Ð¾ÑÐ½Ð¾Ð²Ñ Ð¿ÑÐ¾ÑÐµÑÑÐ° Ð»ÐµÐ³Ð»Ð° ÑÐ¸ÑÑÐµÐ¼Ð° Â«ÑÑÐµÐ¿Ð»ÐµÐ½Ð½ÑÑÂ» ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½Ð¾Ð³Ð¾ (ASTRA) Ð¸ Ð»ÑÑÐµÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð´Ð¾Ð² (FRTÐ¡), Ð¿Ð¾Ð·Ð²Ð¾Ð»ÑÑÑÐ¸Ñ Ð¿ÑÐ¾ÑÐ»ÐµÐ´Ð¸ÑÑ Ð·Ð° Ð³ÐµÐ½ÐµÑÐ°ÑÐ¸Ð¹ ÑÐ¾ÐºÐ° ÑÐ²Ð»ÐµÑÐµÐ½Ð¸Ñ, Ð° ÑÐ°ÐºÐ¶Ðµ Ð¿Ð¾Ð»Ð½Ð¾Ð²Ð¾Ð»Ð½Ð¾Ð²ÑÑ ÑÐ¸ÑÑÐµÐ¼ (GRILL3D) ÑÐ¿Ð¾ÑÐ¾Ð±Ð½ÑÑ ÑÐ°ÑÑÑÐ¸ÑÐ°ÑÑ ÑÐ¿ÐµÐºÑÑ Ð¸Ð·Ð»ÑÑÐ°ÐµÐ¼ÑÑ Ð²Ð¾Ð»Ð½. ÐÐ°Ðº Ð¸Ð·Ð²ÐµÑÑÐ½Ð¾, Ð´Ð»Ñ Ð´Ð¾ÑÑÐ¸Ð¶ÐµÐ½Ð¸Ñ ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð³Ð¾ Ð¸ ÑÑÑÐ¾Ð¹ÑÐ¸Ð²Ð¾Ð³Ð¾ ÑÐµÐ¶Ð¸Ð¼Ð° ÑÐ°Ð±Ð¾ÑÑ ÑÐµÑÐ¼Ð¾ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾ Ð¿ÑÐ¾Ð¿ÑÑÐºÐ°ÑÑ ÑÐ¾Ðº Ð¿Ð¾ Ð¿Ð»Ð°Ð·Ð¼Ðµ. ÐÐ¼Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ¾Ðº, ÑÐ¾Ð·Ð´Ð°Ð²Ð°ÐµÐ¼ÑÐ¹ Ð²Ð½ÐµÑÐ½Ð¸Ð¼ Ð¸Ð½Ð´ÑÐºÑÐ¾ÑÐ¾Ð¼, Ð½Ðµ ÑÐ¿Ð¾ÑÐ¾Ð±ÐµÐ½ Ð¿ÑÐ¾ÑÐµÐºÐ°ÑÑ Ð±ÐµÑÐºÐ¾Ð½ÐµÑÐ½Ð¾ Ð´Ð¾Ð»Ð³Ð¾, Ð² ÑÐ²ÑÐ·Ð¸ Ñ ÑÑÐ¸Ð¼ Ð²Ð°Ð¶Ð½ÑÐ¼ Ð°ÑÐ¿ÐµÐºÑÐ¾Ð¼ Ð² ÑÐ°Ð·Ð²Ð¸ÑÐ¸Ðµ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ°Ñ ÑÑÐ°Ð»Ð¾ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð¸ ÑÐ¾Ð·Ð´Ð°Ð½Ð¸Ðµ Ð¼ÐµÑÐ¾Ð´Ð¾Ð², ÑÐ¿Ð¾ÑÐ¾Ð±Ð½ÑÑ ÑÑÑÑÐ°Ð½Ð¸ÑÑ ÑÑÑ Ð¿ÑÐ¾Ð±Ð»ÐµÐ¼Ñ. ÐÐ¼ÐµÐ½Ð½Ð¾ Ð¿Ð¾ÑÑÐ¾Ð¼Ñ Ð´Ð°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð½Ð°Ð¿ÑÐ°Ð²Ð»ÐµÐ½Ð° Ð½Ð° Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð³ÐµÐ½ÐµÑÐ°ÑÐ¸Ð¸ ÑÐ¾ÐºÐ° Ð±ÐµÐ·ÑÐ½Ð´ÑÐºÑÐ¸Ð¾Ð½Ð½ÑÐ¼ ÑÐ¿Ð¾ÑÐ¾Ð±Ð¾Ð¼, Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð½ÑÐ¼ Ð½Ð° Ð¿ÐµÑÐµÐ´Ð°ÑÐµ Ð¿ÑÐ¾Ð´Ð¾Ð»ÑÐ½Ð¾Ð³Ð¾ Ð¸Ð¼Ð¿ÑÐ»ÑÑÐ° Ð¾Ñ Ð½Ð¸Ð¶Ð½ÐµÐ³Ð¸Ð±ÑÐ¸Ð´Ð½Ð¾Ð¹ Ð²Ð¾Ð»Ð½Ñ Ðº ÑÐ»ÐµÐºÑÑÐ¾Ð½Ð°Ð¼ Ð¿Ð¾ Ð¼ÐµÑÐ°Ð½Ð¸Ð·Ð¼Ñ ÐÐ°Ð½Ð´Ð°Ñ. ÐÐ°Ðº Ð¸ÑÐ¾Ð³, Ð±ÑÐ»Ð¾ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¾ Ð½ÐµÑÐºÐ¾Ð»ÑÐºÐ¾ ÑÐ°ÑÑÐµÑÐ¾Ð² ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ¾Ð² Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ Â«Ð¤Ð¢-2Â», Ð¿Ð¾Ð»ÑÑÐµÐ½Ñ ÑÐ°Ð´Ð¸Ð°Ð»ÑÐ½ÑÐµ Ð¸ Ð¿Ð¾Ð»Ð¾Ð¸Ð´Ð°Ð»ÑÐ½ÑÐµ Ð¿ÑÐ¾ÑÐ¸Ð»Ð¸ ÑÐ½ÐµÑÐ³Ð¾Ð¿Ð¾Ð³Ð»Ð¾ÑÐµÐ½Ð¸Ñ. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¾ ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ðµ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ð½Ð¾Ð³Ð¾ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Ñ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½ÑÐ¼, Ð´Ð°Ð½Ð° Ð¾ÑÐµÐ½ÐºÐ° Ð²ÐµÐ»Ð¸ÑÐ¸Ð½ Ð¿Ð¾Ð´ÑÐ°Ð´ÐºÐ¸ Ð¸ Ð³ÐµÐ½ÐµÑÐ¸ÑÑÐµÐ¼Ð¾Ð³Ð¾ ÑÐ¾ÐºÐ° ÑÐ²Ð»ÐµÑÐµÐ½Ð¸Ñ. Ð ÑÐ¾Ð¼Ñ Ð¶Ðµ, Ð±ÑÐ»Ð¾ ÑÐ¿Ð¾Ð¼ÑÐ½ÑÑÐ° Ð²Ð°Ð¶Ð½Ð¾ÑÑÑ ÑÑÐµÑÐ° Ð¾ÑÑÐ°ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¿Ð¾Ð»Ñ Ð½Ð° Ð³ÐµÐ½ÐµÑÐ°ÑÐ¸Ñ ÑÐ¾ÐºÐ° Ð½Ð¸Ð¶Ð½ÐµÐ³Ð¸Ð±ÑÐ¸Ð´Ð½ÑÐ¼Ð¸ Ð²Ð¾Ð»Ð½Ð°Ð¼Ð¸. ÐÐ¾Ð»ÑÑÐµÐ½Ð½ÑÐµ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÑ Ð¼Ð¾Ð³ÑÑ Ð¿Ð¾ÑÐ»ÑÐ¶Ð¸ÑÑ Ð´Ð»Ñ Ð´Ð°Ð»ÑÐ½ÐµÐ¹ÑÐµÐ³Ð¾ ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ñ ÑÐ¿ÐµÐºÑÑÐ¾Ð² ÑÐ¾ÑÐ¼Ð¾Ð·Ð½Ð¾Ð³Ð¾ Ð¸Ð·Ð»ÑÑÐµÐ½Ð¸Ñ, Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½Ð¾Ð¹ Ð³ÑÑÐ¿Ð¿Ð¾Ð¹ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° Â«Ð¤Ð¢-2Â», Ñ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ð½ÑÐ¼Ð¸ Ð¿ÑÐ¸ Ð¿Ð¾Ð¼Ð¾ÑÐ¸ ÑÑÐ½ÐºÑÐ¸Ð¹ ÑÐ°ÑÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ ÑÐ»ÐµÐºÑÑÐ¾Ð½Ð¾Ð² Ð¿Ð¾ ÑÐºÐ¾ÑÐ¾ÑÑÑÐ¼.
description: This work is devoted to complex modeling of experiments on the FT-2 tokamak, taking into account both the evolution of the main parameters of the plasma column and their radial profiles. The process is based on a system of Â«linkedÂ» transport (ASTRA) and beam codes (FRTÐ¡), which allow tracking the generation of entrainment current, as well as full-wave systems (GRILL3D) capable of calculating the spectrum of emitted waves. As is known, to achieve a stationary and stable operating mode of a thermonuclear reactor, it is necessary to pass current through the plasma. The ohmic current created by an external inductor is not able to flow indefinitely; therefore, an important aspect in the development of tokamaks was the research and creation of methods that can eliminate this problem. That is why this work is aimed at studying the generation of current in a non-inductive manner, based on the transfer of a longitudinal impulse from the lower hybrid wave to electrons according to the Landau mechanism. As a result, several calculations of experiments on the FT-2 tokamak were carried out, and radial and poloidal energy absorption profiles were obtained. The calculated voltage on the bypass of the tokamak is compared with the experimental one, and the values of the boost and the generated entrainment current are estimated. In addition, the importance of taking into account the residual electric field on current generation by lower hybrid waves was mentioned. Ñ The results obtained can serve for further comparison of the bremsstrahlung spectra obtained by the experimental group of the tokamak Â«FT-2Â» with those calculated using electron velocity distribution functions.