Mr
Kaiming Feng
(Southwestern Institute of Physics)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The current design of Chinese Heilum-cooled Ceramic Breeder Test Blanket Module (HCCB TBM) with 1×4 configuration scheme, it includes 4 independent breeding sub-modules with 10mm gap (for thermal expansion) between each other along the poloidal direction. Tthese sub-modules are connected with a big back plate containing auxiliary connection pipes for coolant and purge gas, shear keys and...
Mr
ABHISHEK SARASWAT
(InIPR)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Liquid Lead Lithium (Pb-16Li) is of primary interest as one of the candidate materials for coolant fluid and tritium breeder in liquid metal blanket concepts relevant to fusion power plants. For effective and reliable operation of such high temperature liquid metal coolant systems, monitoring and control of critical process parameters like pressure, level, temperature and flow is essential....
Dr
Choong-Seock Chang
(Princeton Plasma Physics Laboratory and KAIST)
19/10/2016, 14:00
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Poster
The edge gyrokinetic code XGC1 shows that the divertor heat flux width λq in between ELMs of Type I ELMy H-modes in two representative types of present tokamaks (DIII-D type for conventional aspect ratio and NSTX type for tight aspect ratio) is set mostly by the ion neoclassical orbit spread, which is proportional to 1/Ip, while the blobby turbulent spread plays a minor role. This explains the...
Dr
Italo Ricapito
(Fusion for Energy)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The general objective of the ITER TBM Program is to provide the first experimental data on the performance of the breeding blankets in the integrated fusion nuclear environment. Such data are essential to design and predict the performance of DEMO and future fusion reactors. To achieve this objective, the TBM programme will have to: • test and validate technologies and materials in a fusion...
Dr
Masayuki Ono
(PPPL/Princeton University)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady-state fusion power plant designs present major divertor technology challenges, including high divertor heat flux both in steady-state and during transients. In addition to these concerns, there are the unresolved technology issues of long term dust accumulation and associated tritium inventory and safety issues. It has been suggested that radiation-based liquid lithium (LL) divertor...
Dr
Daniel Carralero
(IPP Garching)
19/10/2016, 14:00
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Heat and particle transport onto plasma-facing components is a key issue for next generation tokamaks, as it will determine the erosion levels and the heat loads at the main chamber first wall. In the Scrape-off Layer (SOL), this transport is thought to be dominated by the perpendicular convection of filaments. In this work, we present recent experiments which have led to an improved picture...
Dr
Ilya Senichenkov
(Peter the Great Saint Petersburg Polytechnic University)
19/10/2016, 14:00
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Poster
Our current understanding of divertor physics indicates that at least partial detachment will be a necessary condition for operation of future fusion power devices such as ITER, DEMO and beyond. In recent years a divertor operation with complete detachment was achieved in full tungsten ASDEX Upgrade with nitrogen seeding [Potzel et al Nucl. Fusion 54 (2014) 013001, Reimold et al Nucl. Fusion...
Dr
Holger Reimerdes
(Ecole Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas)
19/10/2016, 14:00
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Present research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models to strengthen the predictive capabilities and improving the operating regime and the divertor configuration. The TCV tokamak is used in particular to investigate to what extent geometric modifications of the configuration can affect the plasma exhaust performance by decreasing the...
Dr
Adam McLean
(Lawrence Livermore National Laboratory)
19/10/2016, 14:00
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
A comprehensive experimental campaign at DIII-D has advanced understanding and modeling of the effects of drifts and radiating species in diverted plasma up to ITER-relevant collisionality. Unique diagnostic capabilities are employed to show directly that plasma drifts lead to in/out asymmetries as well as shifts in radial parameter profiles throughout the divertor legs, and are a critical...
