| 摘要 |
A typical embodiment of an integral pressurized water nuclear reactor and straight-tube steam generator combination in accordance with the invention includes a generally cylindrical pressure vessel that is assembled from three segments which are bolted together at transverse joints to form a fluid and pressure tight unit that encloses the steam generator and the reactor. This novel construction permits primary to secondary coolant heat exchange and improved control rod drive mechanisms which can be exposed for full service access during reactor core refueling, maintenance and inspection. |
