Author/Authors :
Khomutov، نويسنده , , A. I. Barabash ، نويسنده , , V. and Chakin، نويسنده , , V. and Chernov، نويسنده , , Maxine V. and Davydov، نويسنده , , D. and Gorokhov، نويسنده , , V. and Kawamura، نويسنده , , H. and Kolbasov، نويسنده , , B. and Kupriyanov، نويسنده , , I. and Longhurst، نويسنده , , G. and Scaffidi-Argentina، نويسنده , , F. and Shestakov، نويسنده , , V.، نويسنده ,
Abstract :
The main issues for the application of beryllium in fusion reactors are analyzed taking into account the latest results since the ICFRM-9 (Colorado, USA, October 1999) and presented at 5th IEA Be Workshop (10–12 October 2001, Moscow Russia). Considerable progress has been made recently in understanding the problems connected with the selection of the beryllium grades for different applications, characterization of the beryllium at relevant operational conditions (irradiation effects, thermal fatigue, etc.), and development of required manufacturing technologies. The key remaining problems related to the application of beryllium as an armour in near-term fusion reactors (e.g. ITER) are discussed. The features of the application of beryllium and beryllides as a neutron multiplier in the breeder blanket for power reactors (e.g. DEMO) in pebble-bed form are described.
