Abstract
Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increasing the efficiency of a power- generating unit in a nuclear power plantfrom 30-35% at subcritical pressure to 44-45%, reached by the same time at heat and power plants operating at steam pressure ~24 MPa and temperature 560°C and higher. However, the problems which must be solved in this approach delayed the development of reactor facilities with supercritical pressure. One problem is developing reliable methods for calculating the temperature of fuel-element cladding and the hydraulic resistance with water flow at supercritical pressure in the core. This problem is also important because according to current assessments the materials in the core will work at the limit of their possibilities. Possible approaches to a solution of this problem are examined.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.