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Current and future nuclear power reactors and plants 123

Fig. 4.2 Simplified scheme of typical pressurized water reactor (PWR) (Russian VVER-1000)
NPP (ROSENERGOATOM, 2004) [1]: General basic features—(1) thermal neutron
spectrum; (2) uranium dioxide (UO 2 ) fuel; (3) fuel enrichment about 4%; (4) indirect cycle
with steam generator(s) (also, a pressurizer is required (not shown)), i.e., double-flow
circuit (double loop); (5) reactor pressure vessel (RPV) with vertical fuel rods (elements)
assembled in bundle strings cooled with upward flow of light water; (6) reactor coolant
and moderator are the same fluid; (7) reactor-coolant outlet parameters: Pressure 15–16MPa
(T sat ¼342–347°C) and temperatures inlet/outlet 290–325°C; and (8) power cycle—
subcritical-pressure regenerative Rankine steam-turbine cycle with single steam reheat
(working fluid – light water, turbine steam-inlet parameters: Saturation pressure of 6–7MPa
and saturation temperature of 276–286°C).
Courtesy of ROSENERGOATOM. Russian nuclear power plants. 50 Years of nuclear power,
Moscow, Russia; 2004. 120 pp.

(Figs. 4.25–4.27 and Tables 4.1 and 4.9)) and BN-800 (Table 4.9), i.e., the sequence is
based on the decreasing number of particular types of reactors currently operated in
the world (see Table 3.11 inChapter 3).All of the power-conversion cyclesfor current
NPPs are based solely on the subcritical-pressure regenerative and single-steam-
reheat Rankine cycle (for thermal efficiencies of current NPPs, see Table 3.14 in
Chapter 3).
Table 4.1 lists the parameters of Russian power reactors and NPPs, because Russia
has a wide range of operating nuclear power reactors.