Divertor modeling for the design of the National Centralized Tokamak with high beta steady-state plasmas

Fusion Engineering and Design

Volumn 81, Issue 8-14 PART B, 2006, Pages 1613-1620

  Kawashima, H ^a   Sakurai, S ^a   Shimizu, K ^a   Takizuka, T ^a   Tamai, H ^a   Matsukawa, M ^a   Fujita, T ^a   Miura, Y ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

Divertor modeling; Heat load; JT 60U; National Centralized Tokamak; Pumping capability; SOLDOR NEUT2D code

Indexed keywords

COMPUTER SIMULATION; FUSION REACTOR DIVERTORS; HEAT FLUX; PLASMAS; SUPERCONDUCTING DEVICES; THERMAL LOAD;

DIVERTOR MODELING; NATIONAL CENTRALIZED TOKMAK (NCT) FACILITY; PUMPING CAPABILITY;

TOKAMAK DEVICES;

EID: 32544448705     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.07.036     Document Type: Article

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