Page 247 - Dynamics and Control of Nuclear Reactors
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248    APPENDIX B Advanced reactors




                         B.5.3 Pressurized heavy water reactors
                         Canada offers two advanced pressurized heavy water reactor designs. The reactors
                         differ in design and purpose. Brief descriptions follow:
                                                                                    +
                         •  Advanced CANDU Reactor (ACR): The ACR is a Generation III reactor,
                                                                  +
                            designed to compete with other Generation III reactors for service as large
                            central station power plants (Ref. [10]). The main difference from earlier
                            CANDU reactors in the use of light water coolant instead of heavy water. Heavy
                            water moderator in a calandria remains. The ACR employs the principles
                            described in Section B.1. However, the ACR has proved to be non-competitive
                                                       +
                            compared to other Generation III designs and development has been stopped.
                         •  Advanced Fuel CANDU Reactor (AFCR): The Generation III AFCR appears to
                            offer the CANDU reactor a new lease on life. It offers the options of using
                            recycled spent fuel from light water reactors and using low enriched uranium/
                            thorium (LEU//Th) fuel. The AFCR design is basically the same as the CANDU-
                            6, but with new fuel designs [11–13].

                         Spent fuel from light water reactors contains too little fissile material for continued
                         use in the LWR. But the LWR spent fuel contains enough fissile material for use in a
                         CANDU reactor because of CANDU’s better neutron economy (due to heavy water’s
                         small neutron absorption probability).
                            The LEU/Th fuel version enables use of the thorium resource for power produc-
                         tion. The AFCR fuel bundle is cylindrical with 43 concentric fuel rods. The recycled
                         spent fuel version uses 42 rods containing recycled spent fuel and one (centrally
                         located) rods containing a mixture of recycled spent fuel and dysprosium oxide.
                         The LEU/Th version uses eight inner rods containing thorium oxide and thirty-five
                         outer rods containing low enrichment uranium.



                         B.6 Large developmental reactors
                         Several large reactor designs in the developmental stage are potential options for
                         wide-spread implementation. Each design draws on experience with earlier proto-
                         types. Brief descriptions follow:


                         B.6.1 Gas-cooled reactors
                         Magnox, CO 2 cooled power reactors have been operating in Britain for many years,
                         but they were overshadowed by light water reactors developed in other countries. No
                         advanced gas-cooled reactors have been built, but technology development and pro-
                         totype reactor implementation has been pursued.
                            Advanced gas-cooled reactors include prismatic and pebble bed designs (Refs.
                         [14–17]) Prismatic designs have fuel particles embedded in graphite blocks and peb-
                         ble bed designs have fuel particles in graphite balls.
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