Questions raised in developing fast reactor steam generator designs

The most important component in the achievement of satisfactory liquid metal cooled fast breeder reactor reliability is the steam generator. When the failure statistics of other nuclear steam generators and the implications of a sodium-water reaction are considered, there is some cause for concern. It is apparent that considerable improvement in technology is necessary, and until more experience on operating plant is available a conservative design approach must be taken. Many solutions have been proposed varying from forced circulation straight-tube modular to large single-vessel once-through helical designs. Questions are posed that are considered to be the main ones which arise when making a choice of fast reactor steam generator type and tube configuration. The aim is to promote discussion on the relative design approaches, and the importance placed upon the various factors in reaching the goal of ensuring the success of the liquid metal cooled fast breeder reactor in its essential role of conserving world energy resources. (author)