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1 Introduction 1.1 Motivation The reduction of the cost of electricity produced by nuclear power plants is a crucial step toward the successful future utilization of nuclear power. In achieving this goal most work and effort in the past has been directed toward the simplification and cost reduction of primary systems. However, the balance of plant is a large contribution to the cost of the nuclear plant and accounts for about 30% or so of the capital cost. Therefore, efforts to redesign and reduce the cost of power cycles have to be performed as well. Moreover, the sustainability goals set for Generation IV reactors can be enhanced if cycle efficiency is increased. Thus, a power cycle with high efficiency that has small primary resource consumption is sought. Compared to steam cycles, closed cycle gas turbines are in general simple, compact, less expensive and have shorter construction periods, thus reducing the interest during construction. Due to their simplicity they are well suited to modular construction techniques. Therefore, they are a primary topic of current advanced power cycle research. The most mature among the closed gas turbine cycles is the helium Brayton cycle. However helium Brayton cycles require core outlet temperatures around 900 oC in order to achieve attractive efficiencies (~ 45 – 48%). The ESKOM PBMR development program in South Africa is currently the furthest along of several projects aimed at proving out the use of the helium Brayton cycle. However, the high temperature used in this pebble bed reactor may prove to be difficult to accommodate especially when very high goals are set for the plant capacity factor. Thus a prolonged development program for the helium Brayton cycle may be necessary in order to improve its reliability, particularly for direct cycle applications. The high temperature environment required for helium Brayton cycles, and for any ideal gas cycle in general, is challenging to structural materials, and metal-based nuclear fuels are also disqualified. Therefore a power conversion cycle that would be capable of 1PDF Image | Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
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