Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 154 / Number 3 / Pages 265-282
Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Nuclear Technology / Volume 154 / Number 3 / Pages 265-282
Format:electronic copy (download)
Supercritical carbon dioxide cycles are a promising power conversion option for future nuclear reactors operating with a reactor outlet temperature in the range of 550 to 650°C. The recompression cycle version operating with ~20-MPa turbine inlet pressure achieves similar cycle efficiencies as helium Brayton cycles operating at ~250°C higher turbine inlet temperature. The simplicity and high efficiency of the recompression cycle makes it a prime option from among the family of supercritical carbon dioxide cycles. The elimination of the need for intercooling due to the small required compressor work (because of the high density close to the critical point) makes the recompression cycle even simpler than helium Brayton cycles, which require intercooling to achieve attractive efficiencies. The high operating pressure reduces the size of the plant components significantly, making it a promising power cycle for low-cost modularized electricity-generating nuclear systems. However, the real gas behavior that improves the cycle efficiency presents a challenge for part-load operation. The traditional inventory control used for helium Brayton cycles may not be feasible. Bypass control is thus the prime option for part-load operation, making the cycle less efficient than during base-load operation. Since nuclear power plants are operated almost exclusively in base load, this drawback is not a disqualifying blemish.
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