Faites connaître cette offre !
Reference : UMR7340-SOPBAU-017
Workplace : MARSEILLE 13
Date of publication : Wednesday, November 10, 2021
Type of Contract : FTC Technical / Administrative
Contract Period : 6 months
Expected date of employment : 1 December 2021
Proportion of work : Full time
Remuneration : between 2172 and 2769 euros gross per month
Desired level of education : 3-year university degree
Experience required : Indifferent
The objective of this work is to study the relationship between the plasma density at the separator between the closed and open field line regions at the outer mid-plane and the density at the divertor targets as a function of the e-engineer parameters. Using a large database of JET and WEST tokamaks, a series of numerical simulations will be performed to evaluate the impact of magnetic and wall geometries, particularly in the divertor region, on the plasma density and temperature profiles. By combining the simulation and experimental results, a scaling law will be derived. This work will thus provide essential insights into how to improve the predictability of performance for future ITER operation.
A 6-month engineering position is open at the M2P2 laboratory in Marseille, in close collaboration with the IRFM CEA Cadarache, to develop the numerical modeling of this problem. This work will be based on the Soledge2D-EIRENE code (Bufferand et al. 2015), a state-of-the-art numerical platform developed by the project partners to simulate transport at the periphery of tokamaks. This work will also be carried out in close connection with experiments on the WEST tokamak (http://west.cea.fr/fr/index.php), which is operated by CEA in Cadarache, 80 km north of the M2P2 laboratory site.
Candidates must have proven knowledge in plasma physics and advanced skills in numerical modeling and simulation tools.
Power extraction is one of the major challenges on the roadmap of a magnetic confinement nuclear fusion reactor. One of the strategies under investigation to control the heat fluxes impacting the wall, and in particular the divertor targets, is to consider more complex magnetic divertor geometries compared to the standard X-point configuration, such as the "snowflake" or "super-X" configuration. From the studies based on reduced models, it is expected that these geometries favor the reduction of the maximum heat flux on the wall thanks, for example, to an easier access to the "detached" regime as well as to a better dissipation of the plasma power by radiation. To better understand the plasma behavior in these complex magnetic configurations, an efficient simulation tool is needed to correctly estimate the heat and particle flux in the divertor region. In addition, a more detailed description of the plasma detachment process from the wall is required in order to develop control strategies for this operating regime.
Constraints and risks
We talk about it on Twitter!