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Current and future nuclear power reactors and plants              147



            Table 4.9 Continued
            No.  Parameter             BN-600        BN-800       BN-1200
            8    Temperature of power-  240/505      210/490      275/510
                 cycle working fluid: water/
                 steam—T in /T out (°C)
            9    Pressure at steam-generator  13.7   14.0         17.0
                 outlet (MPa)
            10   Scheme of steam       Sodium        Steam        Steam
                 reheat with
            11   Basic unchangeable    30            40           60
                 components service term
                 (years)
            12   Number of fuel assemblies  371      565          432
            13   Fuel enrichment (%)   17; 21; 26    20; 22; 25   –
                                                     (for MOX)
            14   Average fuel burnup   70            70–100       up to 138
                            1
                 (MWday (kg) )
            15   Continues reactor operation  120–170  155        330
                 between refueling intervals
                 (eff. days)
            16   NPP thermal efficiency  42.5        41.9         43.6
                 (gross) (%)
            17   NPP thermal efficiency  40.0        38.8         40.5
                 (net) (%)
            18   Plant capacity factor  0.77–0.8     0.85         0.9
            19   Service life (years)  45            45           60

            a
            BN-600 and BN-800 are currently in operation at the Beloyarsk NPP; BN-600 commercial start—1981
            and BN-800—2015.
            b
            BN-1200—Generation IV concept of future Russian SFR.
                                                          1
           and (c) maximum single-channel mass-flow rate 28.5kgs ; (8) online refueling; and
           (9) power cycle—subcritical-pressure regenerative Rankine steam-turbine cycle with
           steam reheat (working fluid light water; turbine: one High-Pressure (HP) and two
           double-flow Low-Pressure (LP) cylinders; net thermal output 2080MW th ; gross/net
           electrical output (nominal) 740/690MW el ; turbine steam-inlet parameters: saturation
           pressure 4.69MPa and temperature 260°C; feedwater: 5.8MPa (T sat ¼273.4°C) and
           187°C; also, condenser backpressure ranges from 3.74 to 4.9kPa depending on con-
           denser cooling temperature. The T-s diagram for an older CANDU reactor at the Pick-
           ering NPP (i.e., lower steam parameters compared with those of the EC6 reactor) is
           shown in Fig. 4.17.
              A simplified layout of the PHWR NPP (Siemens design, Atucha, Argentina) is
           shown in Fig. 4.18. This is the PHWR design that uses a reactor vessel as the
           reactor-coolant pressure boundary with fuel channels inside, while the CANDU-type
           of PHWR uses the pressure tube in a fuel channel as the pressure boundary. (For
           PHWRs operated in India, see reference [1].)
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