Page 16 - Dynamics and Control of Nuclear Reactors
P. 16

2.3 Generation II reactors     7













                                                   Steamline
                        Walls made of                                  Containment
                        concrete and                                 Cooling System
                        steel
                        3–5 feet thick
                        (1–1.5 meters)
                                                           Steam
                                 4                       3  Generator
                                                        Reactor  Control
                                                        Vessel  Rods
                                 Turbine
                                 Generator



                                 Heater
                          Condenser

                        Condensate
                        Pumps                         2
                                           Coolant Loop
                                                            Core
                                Feed                        1
                                Pumps




                       Demineralizer                                Pressurizer
                                           Reactor
                                           Coolant
                                           Pumps         Containment   Emergency Water
                                                         Structure     Supply Systems
                  FIG. 2.1
                  Layout of a typical pressurized water reactor plant.
                                                     Source: U.S. NRC, www.nrc.gov/reactors/pwrs.html.



                     PWRs and BWRs are designated as light water reactors (LWRs) to distinguish
                  them from reactors that use other coolants. Design parameters of a typical commer-
                  cial PWR and a BWR are given in Appendix A.
                     Canada developed the CANDU reactor that uses natural Uranium fuel and heavy
                  water as a coolant and neutron moderator. In a CANDU reactor, heavy water flows
                  over fuel rods and extracts heat. The heated heavy water passes into a U-tube steam
                  generator similar to the type used in PWRs. Fig. 2.5 shows a schematic of a CANDU
                  reactor. CANDU reactors are pressurized heavy water-moderated reactors, often
   11   12   13   14   15   16   17   18   19   20   21