Conveners
ITER Technology: FIP/1
- Oleg Filatov (Russian Federation)
Mr
Yohji Seki
(Japan Atomic Energy Agency)
13/10/2014, 16:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
Through R&D for a plasma facing unit (PFU) of a full-tungsten (W) ITER divertor, Japan Atomic Energy Agency (JAEA) succeeded in demonstrating the durability of the W divertor which endured a repetitive heat load of 20 MW per sqare meter without macroscopic cracks of all W armors. At the beginning of this activity, the bonding technology armor to heat sink was one of the most important key...
Mr
James Paul Gunn
(CEA Cadarache)
13/10/2014, 17:00
Poster
ITER will begin operation with a full W divertor consisting of solid W monoblocks (MB) bonded to CuCrZr water-carrying cooling tubes. We seek to predict heat flux distributions on MBs comparing three models: optical calculations, ion orbit calculations, and PIC. The consequences of five design aspects are analyzed in terms of available models:
(1) Divertor target tilting to shadow leading...
Mr
Norikiyo Koizumi
(Japan)
13/10/2014, 17:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
A heat-treated Nb3Sn cable-in-conduit conductor (CICC) must be inserted into a groove of a radial plate (RP), which is designed to maintain the mechanical and electrical reliability of the insulation of ITER Toroidal Field (TF) coil during its 20 years’ operation. The difference between heat-treated conductor length and RP groove length must be controlled with accuracy of +/-0.05%. JAEA...
Mr
Pierluigi Bruzzone
(Switzerland)
13/10/2014, 17:40
Oral
A
After completing the qualification tests of the ITER cable-in-conduit conductors (CICC), the series manufacture tests are running in the SULTAN test facility in Villigen, Switzerland, with target completion date in 2015. The key test for the conductor samples is the current sharing temperature, Tcs, at the nominal operating field and current, i.e. the maximum temperature at which the...
Ms
Anna Encheva
(Iter Organization)
13/10/2014, 18:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
ITER is incorporating two types of In-Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Modes and VS Coils to provide Vertical Stabilization of the plasma. Strong coupling with the plasma is required in order that the ELM and VS Coils can meet their performance requirements. Accordingly, the IVCs are mounted on the Vacuum Vessel (VV) inner wall, in close proximity to the plasma, just...
Mr
Carlo Sborchia
(ITER Organization)
13/10/2014, 18:20
Oral
A
ITER is a large experimental tokamak device being built to demonstrate the feasibility of fusion power. The main scope of this paper is to report the status of the design and manufacturing activities of two major ITER components, the ITER Vacuum Vessel (VV) and the Cryostat. Both components will provide the necessary high-vacuum required in the case of the VV for plasma operation and...
