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122 Managing Global Warming

4.2 Current nuclear power reactors and NPPs

This section is based on Appendix A1 from the Handbook of Generation IV Nuclear
Reactors [1]; papers by Pioro and Duffey [2] and Dragunov et al. [3]; and chapters by
Pioro and Kirillov [4–6].
This section is dedicated to modern nuclear power reactors and corresponding
to that Nuclear Power Plants (NPPs), and includes typical operating conditions of
selected water-cooled reactors (Fig. 4.1), NPPs layouts (Figs. 4.2–4.6, 4.8–4.10,
4.12–4.14, 4.16, 4.18–4.20, 4.22, 4.23, 4.25, and 4.26), T-s diagrams (Figs. 4.4,
4.11, 4.17, 4.21, 4.24, and 4.27), fuel assemblies (Fig. 4.7), fuel channel
(Fig. 4.15), fuel element (Fig. 4.19B); and basic parameters of nuclear power reac-
tors and NPPs (Tables 4.1–4.9). Nuclear power reactors and corresponding NPPs
are listed in the following sequence: (1) Pressurized water reactors (PWRs)/
advanced PWRs (APWRs) (Figs. 4.2–4.7 and Tables 4.1–4.6); (2) boiling water
reactors (BWRs)/ABWRs (Figs. 4.8–4.11 and Tables 4.7 and 4.8); (3) pressurized
heavy-water reactors (PHWRs) (Figs. 4.12–4.18); (4) Advanced Gas-cooled Reac-
tors (AGRs) (Figs. 4.19–4.21); (5) light-water graphite-moderated reactors (LGRs)
(RBMKs (Figs. 4.22–4.24 and Table 4.1) and EGPs), and (6) liquid-metal fast-
breeder reactors (LMFBRs) (Russian sodium fast reactors (SFRs)—BN-600

Fig. 4.1 Typical operating conditions (pressure drop is not accounted for) in P-T coordinates for
BWRs, CANDU reactors, PWRs, and supercritical water-cooled reactors (SCWRs) (Generation
IV concept) [1].