1.    Overview

    1.1    Short introduction into reactor physics
    1.2    Survey of nuclear power plants (NPP)
    1.3    Present state of NPPs worldwide

2.    Thermal nuclear power plants

    2.1    Pressurized water reactor (PWR)
    2.2    The Three Mile Island accident
    2.3    European pressurized water Reactor (EPR)
    2.4    Boiling water reactor (BWR)
    2.5    Safety engineering
    2.6    Auxiliary systems for LWR
    2.7    Heavy water moderator reactor (HWR)
             2.7.1    Pressurized heavy water moderator reactor (PHWR)
             2.7.2    Pressure tube heavy water moderator reactor (CANDU)
             2.7.3    Steam generating heavy water moderator reactor (SGHWR)
    2.8    Gas cooled reactor (GCR)
             2.8.1    MAGNOX, AGR-reactor
             2.8.2    High temperature gas cooled reactor (HTR)
    2.9    Graphite moderated light water cooled pressure tube reactor (RBMK-type)
    2.10  The Chernobyl accident
    2.11 The Tokai Mura accident

3.    Liquid metal fast breeder reactor (LMFBR)

    3.1    Properties of liquid sodium
    3.2    LMFBR-loop type
    3.3    LMFBR-pool type
    3.4    Auxiliary systems for LMFBR

4.     Generation IV Reactors

    4.1    Gas-Cooled Fast Reactor (GFR)
    4.2    Very-High-Temperature Reactor (VHTR)
    4.3    Supercritical-Water-Cooled Reactor (SCWR)
    4.4    Sodium-Cooled Fast Reactor (SFR)
    4.5    Lead-Cooled Fast Reactor (LFR)
    4.6    Molton Salt Reactor (MSR  

5.    Common auxiliary systems

    5.1    Normal and emergency power supply
    5.2    Radioactive waste treatment system in NPP

6.    Decommissioning of Nuclear Power Plants