Abstract :
The paper commences with a broad examination of the likely role of nuclear power in relation to other sources of primary energy for electricity generation in the UK, and then briefly reviews the historical reasons for the choice of different types of reactors in various countries. The design and operational performance of the Mk. I gas-cooled-reactor stations (Magnox) of the UK´s first nuclear-power programme are fully discussed. The paper continues with an account of the progress to date in the design and construction of the Mk. II gas-cooled reactor, stations (a.g.r.) of the second nuclear-power programme and a description of the a.g.r. system. Basic descriptions are given of the more advanced types of thermal-reactor systems available for large-scale application and from which a successor or concomitant to the a.g.r. may be chosen, namely the Mk. III gas-cooled reactor, also known as the high-temperature reactor (h.t.r.), and the steam-generating heavy-water reactor (s.g.h.w.r.), and also of the type which should become available for commercial exploitation within a few years, the fast-breeder reactor. The paper concludes by considering the dilemma facing the CEGB in the immediate future before deciding on which more advanced reactor type to adopt. The advantages and disvantages of the four options open to the CEGB¿choice of the h.t.r.s.g.h.w.r. or a light-water reactor, or adherence to the a. g.r.¿are explained. The cost of introducing a more advanced reactor system can be so great that the case for internationally financed launching programmes is indisputable. In spite of the present uncertainties about the direction of nuclear power, there is no dilemma about the merit of nuclear power for electricity generation in the long term.
