Testing of small-scale cavity closure models in support of development of a 300 MW(e) Gas-Cooled fast breeder reactor

Abstract

The Oak Ridge National Laboratory has been involved in design verification and support studies of the prestressed concrete reactor vessel (PCRV) for a 300 MW(e) Gas-Cooled Fast Reactor demonstration power plant. These studies have been related to the design and testing of small-scale models of the steam generator cavity and reactor core cavity closure plugs for the PCRV. The primary objective of these studies was to determine the structural response of the plugs both to normal operating pressure and to substantial overpressurization. Three closure plug models have been tested: a 1 15- scale full-thickness steam generator cavity closure plug, a 1 15- scale half-thickness steam generator cavity closure plug and a 1 20- scale reactor core cavity closure plug. Results obtained indicate that the closure plugs have a significant overload capacity; that is, in excess of 7·5 times the design pressure of the prototype.