STEAM CYCLES FOR GAS-COOLED REACTORS
W.R. Wootton, Abigail L. Taylor, N.G. Worley
Abstract
W.R. Wootton, Abigail L. Taylor, N.G. Worley
Abstract
The potentialities of the steam cycle in association with possible trends in nuclear reactor development are investigated. Attention is confined to gas cooled reactors and emphasis is placed on the most probable coolant temperatures entering the reactor and those likely to be attained in the future at the reactor outlet. The coolant temperature leaving the reactor is assumed to from 350 to 600 deg C and the most prohable steam cycles are found for each stage of development. These lead to an indication of the trend of efficiency of future nuclear steam power plants of the gas-cooled type. (W.D.M.)
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The potentialities of the steam cycle in association with possible trends in nuclear reactor development are investigated. Attention is confined to gas cooled reactors and emphasis is placed on the most probable coolant temperatures entering the reactor and those likely to be attained in the future at the reactor outlet. The coolant temperature leaving the reactor is assumed to from 350 to 600 deg C and the most prohable steam cycles are found for each stage of development. These lead to an indication of the trend of efficiency of future nuclear steam power plants of the gas-cooled type. (W.D.M.)
Key concepts: Coolant, Nuclear engineering, Nuclear power, Nuclear reactor, Environmental science, Waste management, Materials science, Engineering