title: ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ ÑÑÐ°Ð´Ð¸Ð¸ Ð²ÑÐ²Ð¾Ð´Ð° ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐ½ÐµÑÐ³Ð¸Ð¸ Ð¿ÑÐ¸ ÑÑÑÐ²Ðµ ÑÐ¾ÐºÐ° ÑÐ°Ð·ÑÑÐ´Ð° Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ
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 thermal energy loss stage during current quench in tokamak
Creators: name: ÐÐ°Ð³ÑÑÐºÐ¸Ð½, Ð¡Ð°Ð²ÐµÐ»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: ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÑÐ²
ÑÑÑÐ² ÑÐ¾ÐºÐ° ÑÐ°Ð·ÑÑÐ´Ð°
ÑÑÑÐ² ÑÐ°Ð·ÑÑÐ´Ð°
ÑÐºÐ°ÑÐ¾Ðº Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ
Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ
thermal quench
current quench
disruption
voltage spike
simulation

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð²ÑÐµÐ¼ÐµÐ½Ð½Ð¾Ð¹ ÑÐ²Ð¾Ð»ÑÑÐ¸Ð¸ ÑÐ¾ÐºÐ° Ð¿Ð»Ð°Ð·Ð¼Ñ Ð¸ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ° Ð¿Ð¾ÑÐ»Ðµ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð³Ð¾ ÑÑÑÐ²Ð° ÑÐ°Ð·ÑÑÐ´Ð° Ð½Ð° Ð¿ÑÐ¸Ð¼ÐµÑÐµ ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐ° JET. Ð¦ÐµÐ»ÑÑ ÑÐ°Ð±Ð¾ÑÑ ÑÐ²Ð»ÑÐµÑÑÑ Ð½Ð°ÑÐ¾Ð¶Ð´ÐµÐ½Ð¸Ðµ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐµÑÐµÐ½Ð¸Ñ, Ð½Ð°Ð¸Ð»ÑÑÑÐ¸Ð¼ Ð¾Ð±ÑÐ°Ð·Ð¾Ð¼ Ð¿ÑÐ¸Ð±Ð»Ð¸Ð¶ÐµÐ½Ð½Ð¾Ð³Ð¾ Ðº ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½ÑÐ¼Ð¸ Ð´Ð°Ð½Ð½ÑÐ¼ ÑÑÑÐ²Ð° ÑÐ°Ð·ÑÑÐ´Ð° Ð½Ð° JET Ð¸ Ðº ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¸Ð· ÑÑÐ°ÑÑÐ¸ J.A. Wesson et al 1990 Nucl. Fusion 30 1011. ÐÐ¾ÑÑÑÐ¾ÐµÐ½Ð¸Ðµ Ð´Ð°Ð½Ð½Ð¾Ð¹ Ð¼Ð¾Ð´ÐµÐ»Ð¸ Ð´Ð°ÐµÑ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½Ð¾ÑÑÑ Ð±Ð¾Ð»ÐµÐµ ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ð³Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐ²Ð¾Ð»ÑÑÐ¸Ð¸ ÑÐ¾ÐºÐ° Ð¿Ð»Ð°Ð·Ð¼Ñ Ð¸ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ° Ð¿Ð¾ÑÐ»Ðµ ÑÑÑÐ²Ð° ÑÐ°Ð·ÑÑÐ´Ð° Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ. Ð Ð°Ð±Ð¾ÑÐ° Ð±ÑÐ»Ð° Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð° Ð² Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ðµ MathCad 15. Ð ÑÐ¾Ð´Ðµ ÑÐ°Ð±Ð¾ÑÑ Ð±ÑÐ»Ð° ÑÐµÑÐµÐ½Ð° ÑÐ¸ÑÑÐµÐ¼Ð° ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ð¹, ÑÐ²ÑÐ·ÑÐ²Ð°ÑÑÐ¸Ñ ÑÐ¾Ðº Ð¿Ð»Ð°Ð·Ð¼Ñ, ÑÐ¾Ðº Ð¿Ð¾ ÑÑÐµÐ½ÐºÐµ Ð²Ð°ÐºÑÑÐ¼Ð½Ð¾Ð¹ ÐºÐ°Ð¼ÐµÑÑ Ð¸ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ðµ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ°. ÐÐ° Ð¾ÑÐ½Ð¾Ð²Ðµ Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ¸ÑÑÐµÐ¼Ñ Ð±ÑÐ»Ð° Ð¿Ð¾ÑÑÑÐ¾ÐµÐ½Ð° Ð¾Ð´Ð½Ð¾Ð¼ÐµÑÐ½Ð°Ñ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð°Ñ Ð¼Ð¾Ð´ÐµÐ»Ñ Ð´Ð»Ñ ÑÐ¸Ð¼ÑÐ»ÑÑÐ¸Ð¸ ÑÐ²Ð¾Ð»ÑÑÐ¸Ð¸ ÑÐ¾ÐºÐ° Ð¿Ð»Ð°Ð·Ð¼Ñ Ð¸ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾Ð±ÑÐ¾Ð´Ðµ Ð¿Ð¾ÑÐ»Ðµ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð³Ð¾ ÑÑÑÐ²Ð° ÑÐ°Ð·ÑÑÐ´Ð° Ð² ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ. Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ ÑÐ¸ÑÐ»ÐµÐ½Ð½ÑÑ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ¾Ð² Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð·Ð½Ð°ÑÐµÐ½Ð¸Ñ Ð²Ð·Ð°Ð¸Ð¼Ð½Ð¾Ð¹ Ð¸Ð½Ð´ÑÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ° Ð¸ Ð²Ð°ÐºÑÑÐ¼Ð½Ð¾Ð¹ ÐºÐ°Ð¼ÐµÑÑ Ð¸ ÑÐ°Ð´Ð¸ÑÑÐ° Ð¿ÐµÑÐµÐ¼ÐµÑÐ¸Ð²Ð°Ð½Ð¸Ñ Ð¼Ð°Ð³Ð½Ð¸ÑÐ½Ð¾Ð³Ð¾ Ð¿ÐµÑÐµÐ·Ð°Ð¼ÑÐºÐ°Ð½Ð¸Ñ, Ð¿ÑÐ¸ ÐºÐ¾ÑÐ¾ÑÑÑ Ð¼Ð¾Ð´ÐµÐ»Ñ Ð½Ð°Ð¸Ð»ÑÑÑÐ¸Ð¼ Ð¾Ð±ÑÐ°Ð·Ð¾Ð¼ ÑÐ¾Ð³Ð»Ð°ÑÑÐµÑÑÑ Ñ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼Ð¸ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ, ÐºÐ¾ÑÐ¾ÑÑÐµ Ð¿ÑÐµÐ´ÑÑÐ°Ð²Ð¸Ð» J. A. Wesson, Ð¸ Ñ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½ÑÐ¼Ð¸ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼Ð¸, Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÐ¼Ð¸ Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ JET. ÐÐ· ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð² ÑÐ°Ð±Ð¾ÑÑ Ð¼Ð¾Ð¶Ð½Ð¾ ÑÐ´ÐµÐ»Ð°ÑÑ Ð²ÑÐ²Ð¾Ð´, ÑÑÐ¾ Ð¿ÑÐ¸Ð±Ð»Ð¸Ð¶ÐµÐ½Ð¸Ðµ ÑÐ°Ð´Ð¸ÑÑÐ° Ð¿ÐµÑÐµÐ¼ÐµÑÐ¸Ð²Ð°Ð½Ð¸Ñ Ð¼Ð°Ð³Ð½Ð¸ÑÐ½Ð¾Ð³Ð¾ Ð¿ÐµÑÐµÐ·Ð°Ð¼ÑÐºÐ°Ð½Ð¸Ñ Ðº Ð¼Ð°Ð»Ð¾Ð¼Ñ ÑÐ°Ð´Ð¸ÑÑÑ Ð¿Ð»Ð°Ð·Ð¼ÐµÐ½Ð½Ð¾Ð³Ð¾ ÑÐ½ÑÑÐ° ÑÐ»ÑÑÑÐ°ÐµÑ ÑÐ¾Ð³Ð»Ð°ÑÐ¾Ð²Ð°Ð½Ð½Ð¾ÑÑÑ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ð½ÑÑ ÑÐ¸Ð³Ð½Ð°Ð»Ð¾Ð² Ñ Ð¸Ð·Ð¼ÐµÑÐµÐ½Ð½ÑÐ¼Ð¸ Ð½Ð° ÑÐ¾ÐºÐ°Ð¼Ð°ÐºÐµ JET.
description: The given work is devoted to modeling the temporal evolution of plasma current and loop voltage after thermal quench using the example of JET tokamak. The aim of the work is to find a numerical solution that best approximates the experimental data on discharge disruption at JET and the simulation results from the article J.A. Wesson et al 1990 Nucl. Fusion 30 1011. Creation of this model makes it possible to more accurately numerically simulate the evolution of plasma current and loop voltage along plasma column after disruption in tokamak. The work was carried out in the MathCad 15 program. During the work, a system of equations relating plasma current, current along the wall of vacuum vessel and loop voltage along plasma column was solved. Based on this system, a one-dimensional numerical model was created to simulate the evolution of the plasma current and loop voltage after thermal quench of discharge in tokamak. As a result of numerical experiments, the values of mutual inductance of plasma column and vacuum vessel and the magnetic reconnection mixing radius were determined, at which the model best agrees with the simulation results presented by J. A. Wesson and with the experimental results obtained on the JET tokamak. From the results of the work, one can conclude that approaching of magnetic reconnection mixing radius closer to minor radius of plasma column improves the consistency of the calculated signals with those measured at the JET tokamak.