DocumentCode :
227471
Title :
Effect of edge plasma radiation on erosion and damage to iter plasma facing and nearby components
Author :
Sizyuk, Valeryi ; Hassanein, A.
Author_Institution :
Center for Mater. Under Extreme Environ., Purdue Univ., West Lafayette, IN, USA
fYear :
2014
fDate :
25-29 May 2014
Firstpage :
1
Lastpage :
1
Abstract :
Edge plasma behavior plays an essential role in the success of fusion devices by setting the boundary condition for the core plasma. Comprehensive understanding of tokamak edge plasma transport is important for several reasons including plasma stability and heat loads and lifetime of plasma-facing components (PFCs). During normal and disruptive operations in tokamak devices, radiation transport processes play important role in edge plasma dynamic and can be an indirect potential threat to the divertor and nearby components lifetime as well as the direct escaped core plasma impact. The recent upgraded HEIGHTS simulation package1,2 proved the necessity of integrated detail edge plasma transport in the whole SOL area domain. In particular, modeling of impurity contaminations drift with fine details of radiation transport to nearby component surfaces. In coupling with the earlier developed kinetic model of the core plasma escaping3, the radiation transport model was used for simulation of giant ELMs and disruptions in the current design of ITER device. This hybrid approach was enhanced using adaptive mesh refinement for mapping the complex 3D geometry of device walls and implementing nanoscale surface processes. The surfaces response to radiation fluxes from the evolving divertor plasma as a result of intense power deposition has been numerically modeled. Calculations show in agreement with previous studies2 the significant increase in radiation fluxes and damage risk of nearby divertor components during disruptions. From the same plasma core impact energy, the radiation fluxes from the developed divertor plasma increase with the material atomic number. The detailed radiation spectra were calculated and compared for carbon and tungsten as divertor plate materials. Significant damage risk was predicted for the open stainless steel legs of the dome in current ITER design during disruptions from tungsten-made divertor plates.
Keywords :
Tokamak devices; carbon; fusion reactor divertors; plasma boundary layers; plasma simulation; plasma toroidal confinement; plasma transport processes; plasma-wall interactions; tungsten; C; EROSION; ITER; SOL area domain; W; adaptive mesh refinement; carbon-divertor plate materials; complex 3D nanoscale surface process; damage risk; divertor plasma; edge plasma dynamic; edge plasma radiation transport behavior; fusion devices; heat loads; hybrid approach; impurity contamination drift; kinetic model; material atomic number; numerical analysis; plasma core impact energy; plasma disruptions; plasma facing component lifetime; plasma stability; radiation flux; radiation spectra; stainless steel; tokamak devices; tungsten-divertor plate materials; upgraded HEIGHTS simulation package; Adaptation models; Boundary conditions; Educational institutions; Kinetic theory; Materials; Plasmas; Surface treatment;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Plasma Sciences (ICOPS) held with 2014 IEEE International Conference on High-Power Particle Beams (BEAMS), 2014 IEEE 41st International Conference on
Conference_Location :
Washington, DC
Print_ISBN :
978-1-4799-2711-1
Type :
conf
DOI :
10.1109/PLASMA.2014.7012381
Filename :
7012381
Link To Document :
بازگشت