| 摘要 |
<p>A system for discharging the residual power of a fast breeder nuclear reactor, using forced convection in the inter-vessel space. The reactor, which is preferably cooled using liquid sodium, comprises a main vessel (44) and a safety vessel (46), separated from the main vessel by an inter-vessel space (48) filled with a gas which is chemically inert in relation to sodium. The two vessels each have a cylindrical upper portion (50, 51), around a common vertical geometric axis (X), and a lower portion (52, 53). According to the invention, the system comprises a device (49) for rotating the gas, for example in the inter-vessel space, about the common axis, at least over the height of the upper portion of the main vessel, in order to transfer the heat from the main vessel to the safety vessel by means of forced convection.</p> |
