Steam generator or heater for an atomic power generating plant

Abstract

Abstract 1,177,533. Generating steam by indirect heat transfer. JAPAN ATOMIC ENERGY RESEARCH INSTITUTE and NIPPON KOHKAN K.K. 13 Jan., 1967 [14 Jan., 1966], No. 1913/67. Heading F4A. Liquid sodium coolant from a nuclear reactor (not shown) is passed through vertical tubes 2 extending between inlet nozzle 1 and outlet nozzle 3 of a steam generator casing 7. Water from inlet 4 flows in counter current through vertical, zig-zag or helical tubes 5, the steam so generated emerging through nozzle 6. Heat is transferred between the tube systems 2, 5 by liquid sodium acting as a heat transmission medium, which is introduced at inlet 9 and removed through outlet 10, to maintain a surface level 11. The level 11 may be varied to vary the rate of heat transfer in accordance with the load demand. The top space of the generator body contains an inert gas introduced through nozzle 13 and removed through nozzle 14. One or more rupture discs 15 may be provided in the casing 7. The generator may be of the through flow or recirculation types. It is stated to be known to heat an intermediate fluid by the coolant from the reactor core, in a separate heat exchange vessel located within or without the vessel containing the reactor, and then to circulate this intermediate fluid over steam generating tubes contained in a further vessel (Figs. 1 and 2, not shown).

Inventors

• 👤 Masao Nozawa
• 👤 Kiyoshi Sako
• 👤 Hiroshi Ueda

Bibliographic Details