Community Research and Development Information Service - CORDIS


One of the main concerns related to NET and to future fusion plants is the residual power stocked in the internal reactor structures, because of the important hazards which could occur in cases of loss of cooling flow accidents (LOFA). At present only the case of electric black-out, followed by an inherent plasma shut-down and loss of the pumping capability has been studied. The cooling circuit of the inboard first wall/divertor system (IFW) is designed to allow a thermosiphon effect which is able to remove the total residual power, generated in the reactor structures and transferred to the circuit by means of conduction and radiation effects. The circuit is integrated with the actual NET general design and with the building.

Additional information

Authors: RENDA V, JRC Estab. (IT);FENOGLIO F, Politecnico di Torino (IT)
Bibliographic Reference: Paper presented: 15th Symposium on Fusion Technology, Utrecht (NL), Sept. 19-23, 1988
Availability: Available from (1) as Paper EN 34213 ORA
Record Number: 198910510 / Last updated on: 1994-12-01
Original language: en
Available languages: en
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