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Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (Scwrs): IAEA Tecdoc Series No. 1746
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Inhalt: |
The supercritical water cooled reactor (SCWR) is an innovative water cooled reactor concept which uses water pressurized above its thermodynamic critical pressure as the reactor coolant. This concept offers high thermal efficiencies and a simplified reactor system, and is hence expected to help to improve economic competitiveness. Various kinds of SCWR concepts have been developed, with varying combinations of reactor type (pressure vessel or pressure tube) and core spectrum (thermal, fast or mixed). There is great interest in both developing and developed countries in the research and development (R&D) and conceptual design of SCWRs. This publication consists of the background and objectives, descriptions of current SCWR design concepts, and major technical achievements from the CRP tasks based on the results of R&D at participating institutes and through their close collaboration. It provides researchers and engineers with a comprehensive and reliable database. |
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