Physics drivers for the plasma-facing component design of the COMPASS-U tokamak

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F25%3A00648062" target="_blank" >RIV/61389021:_____/25:00648062 - isvavai.cz</a>

Výsledek na webu

<a href="https://iopscience.iop.org/article/10.1088/1361-6587/addc98" target="_blank" >https://iopscience.iop.org/article/10.1088/1361-6587/addc98</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/1361-6587/addc98" target="_blank" >10.1088/1361-6587/addc98</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Physics drivers for the plasma-facing component design of the COMPASS-U tokamak

Popis výsledku v původním jazyce

The main drivers for the metallic plasma-facing component (PFC) design of the COMPASS Upgrade (COMPASS-U) tokamak (BT <= 5 T, IP <= 2 MA, Rgeo = 0.9 m, ageo = 0.27 m, tflattop <= 3 s) derived from physics considerations are presented in this paper. Requirements on the plasma-wall gaps are given based on previous experimental observations in other devices. Gaps at the inner/outer midplane are set to minimum values 20 and 40 mm, respectively, to allow all magnetic equilibria in the lower and upper single-null configurations to fit in the PFC outline, to allow an efficient flow in the scrape-off layer towards the divertor and to minimize the impurity flux from the wall. The closed tungsten divertor was designed with a similar shape to ITER's divertor since COMPASS-U has a similar aspect ratio and uses an ITER-like equilibrium for its baseline scenario. Steady-state thermal loads are calculated at the outer strike-point, where they are expected to be the highest, in attached conditions using a 0D energy balance (>= 150 MW m-2) and in detached conditions using BIT1 kinetic calculations (similar to 70 MW m-2). Transient thermal loads range from 1.2 MJ m-2 for ELMs (maximum parallel peak energy fluence at targets) to 0.6-1.2 GW m-2 in similar to 0.5 ms for high-energy vertical displacement events (maximum perpendicular heat flux density). Electromagnetic loads are calculated during disruptions using an in-house parametric model, accounting for current quench (CQ) and halo current contributions and validated by simulations using the CarMa0NL code, which is able to describe the nonlinear evolution of axisymmetric plasmas in the presence of 3D volumetric structures. The CQ rate is expected to be at least delta IP/delta t = 3 MA ms-1, and the halo current magnitude is set to 75% of the pre-disruptive maximum plasma current, according to the ITPA disruption database, yielding Ihalo = 1.5 MA. Maximum total force acts on the bottom divertor baffle with a value of similar to 60 kN and the corresponding total torque is similar to 4 kN m.

Název v anglickém jazyce

Physics drivers for the plasma-facing component design of the COMPASS-U tokamak

Popis výsledku anglicky

The main drivers for the metallic plasma-facing component (PFC) design of the COMPASS Upgrade (COMPASS-U) tokamak (BT <= 5 T, IP <= 2 MA, Rgeo = 0.9 m, ageo = 0.27 m, tflattop <= 3 s) derived from physics considerations are presented in this paper. Requirements on the plasma-wall gaps are given based on previous experimental observations in other devices. Gaps at the inner/outer midplane are set to minimum values 20 and 40 mm, respectively, to allow all magnetic equilibria in the lower and upper single-null configurations to fit in the PFC outline, to allow an efficient flow in the scrape-off layer towards the divertor and to minimize the impurity flux from the wall. The closed tungsten divertor was designed with a similar shape to ITER's divertor since COMPASS-U has a similar aspect ratio and uses an ITER-like equilibrium for its baseline scenario. Steady-state thermal loads are calculated at the outer strike-point, where they are expected to be the highest, in attached conditions using a 0D energy balance (>= 150 MW m-2) and in detached conditions using BIT1 kinetic calculations (similar to 70 MW m-2). Transient thermal loads range from 1.2 MJ m-2 for ELMs (maximum parallel peak energy fluence at targets) to 0.6-1.2 GW m-2 in similar to 0.5 ms for high-energy vertical displacement events (maximum perpendicular heat flux density). Electromagnetic loads are calculated during disruptions using an in-house parametric model, accounting for current quench (CQ) and halo current contributions and validated by simulations using the CarMa0NL code, which is able to describe the nonlinear evolution of axisymmetric plasmas in the presence of 3D volumetric structures. The CQ rate is expected to be at least delta IP/delta t = 3 MA ms-1, and the halo current magnitude is set to 75% of the pre-disruptive maximum plasma current, according to the ITPA disruption database, yielding Ihalo = 1.5 MA. Maximum total force acts on the bottom divertor baffle with a value of similar to 60 kN and the corresponding total torque is similar to 4 kN m.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2025

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Plasma Physics and Controlled Fusion

ISSN

0741-3335

e-ISSN

1361-6587

Svazek periodika

67

Číslo periodika v rámci svazku

6

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

14

Strana od-do

065030

Kód UT WoS článku

001505480200001

EID výsledku v databázi Scopus

2-s2.0-105008149574