Results 71 to 80 of about 466 (242)

Assessment of X-point target divertor configuration for power handling and detachment front control

Nuclear Materials and Energy, 2017
A study of long-legged tokamak divertor configurations is performed with the edge transport code UEDGE (Rognlien et al., J. Nucl. Mater. 196, 347, 1992). The model parameters are based on the ADX tokamak concept design (LaBombard et al., Nucl. Fusion 55,
M.V. Umansky, M.E. Rensink, T.D. Rognlien, B. LaBombard, D. Brunner, J.L. Terry, D.G. Whyte   +6 more
doaj   +1 more source

Poloidal Pressure Gradients, Divertor Detachment and Marfes [PDF]

Contributions to Plasma Physics, 1998
AbstractBecause the radiation power density from a marfe scales approximately as the square of its plasma pressure, and since increased radiation would aid divertor detachment for high power tokamaks, this paper identifies regions that might permit locally increased plasma pressure in steady state. The magnetic and dynamic (flow) constraints of magneto‐
openaire   +1 more source

Digital Transformation in Work Integration Social Enterprises: Leadership Strategies and the Role of Internal Stakeholders

Corporate Social Responsibility and Environmental Management, EarlyView.
ABSTRACT Digital transformation is increasingly reshaping how social enterprises organize work, engage stakeholders, and pursue social value. While prior research has examined digitalization in hybrid organizations, limited attention has been paid to how responsibility for inclusive digital transformation is enacted internally.
Riccardo Maiolini, Federica D’Alessandro, Paolo Landoni   +2 more
wiley   +1 more source

SOLPS-ITER modeling of divertor detachment in MAST-U’s super-X double null configuration and comparison to experiment

Nuclear Materials and Energy
The MAST-U tokamak has recently undergone upgrades to investigate any detachment advantages of the “Super-X Double-Null” magnetic configuration, a concept featuring up-down symmetry with two magnetic nulls and elongated divertor legs with strong wall ...
R. Maurizio, A.W. Leonard, J.H. Yu, J. Harrison, K. Verhaegh, N. Lonigro, A.G. McLean   +6 more
doaj   +1 more source

Detachment control in KSTAR with Tungsten divertor

KSTAR has recently undergone an upgrade to use a new Tungsten divertor to run experiments in ITER-relevant scenarios. Even with a high melting point of Tungsten, it is important to control the heat flux impinging on tungsten divertor targets to minimize sputtering and contamination of the core plasma.
Gupta, Anchal, Eldon, David, Bang, Eunnam, Kwon, KyuBeen, Lee, Hyungho, Leonard, Anthony, Hwang, Junghoo, Xu, Xueqiao, Zhao, Menglong, Zhu, Ben   +9 more
openaire   +2 more sources

An Estimation of the Heat Load Distribution on the Divertor Target Using the CSD Model

Contributions to Plasma Physics, EarlyView.
ABSTRACT Handling the heat load on the divertor target is a critical issue in the design of fusion reactors. Estimating the heat load, supported by computationally efficient simulations with varying design parameters, provides valuable input to high‐level design discussions and the development of design guidelines.
Kazuhiro Yamada, Kazuo Hoshino, Gakushi Kawamura, Hang Si, Akiyoshi Hatayama   +4 more
wiley   +1 more source

Cryopump and fuelling location impacts on upstream density and detachment on MAST-Upgrade

Nuclear Fusion
A cryopump was installed in the MAST Upgrade (MAST-U) lower divertor at the start of its fourth scientific campaign (MU04) to enhance density control, detachment front management, and impurity removal, while expanding the operational space to lower ...
Q. Xia, D. Moulton, J.R. Harrison, H.J. Sun, K. Verhaegh, N. Osborne, N. Lonigro, P. Ryan, the MAST Upgrade Team   +8 more
doaj   +1 more source

Coupling Fluid Neutrals to Gyrokinetic Plasma Dynamics for Edge and SOL Turbulence Simulations

Contributions to Plasma Physics, EarlyView.
ABSTRACT Accurate modeling of turbulent transport in magnetic confinement fusion devices requires extending first‐principles gyrokinetic simulations from the core to the edge and scrape‐off layer (SOL), where additional physics—particularly plasma–neutrals interactions—must be included.
Sabine Ogier‐Collin, Philipp Ulbl, Wladimir Zholobenko, Frank Jenko   +3 more
wiley   +1 more source

Experimental research on the deeply detached X-point radiator regime on EAST

Nuclear Fusion
Radiative divertor detachment with impurity seeding is considered one of the most promising means for mitigating particle and heat fluxes on the divertor target.
Baoguo Wang, Rong Yan, Kedong Li, Dahuan Zhu, Rui Ding, Beihe Zhang, Kai Wu, Xin Lin, Binfu Gao, Lingyi Meng, Jianhua Yang, Lin Yu, Yanmin Duan, Jinju Yang, Kangning Geng, Qing Zhang, Tao Zhang, Fudi Wang, Yifei Jin, Hailin Zhao, Bin Zhang, Pengfei Zhou, Chunyu He, Yang Wang, Liang Wang, Junling Chen, the EAST Team   +26 more
doaj   +1 more source

Experimental studies of the snowflake divertor in TCV

Nuclear Materials and Energy, 2017
To address the risk that, in a fusion reactor, the conventional single-null divertor (SND) configuration may not be able to handle the power exhaust, alternative divertor configurations, such as the Snowflake divertor (SFD), are investigated in TCV.
B. Labit, G.P. Canal, N. Christen, B.P. Duval, B. Lipschultz, T. Lunt, F. Nespoli, H. Reimerdes, U. Sheikh, C. Theiler, C.K. Tsui, K. Verhaegh, W.A.J. Vijvers   +12 more
doaj   +1 more source