抄録
This paper focuses on a generic Pressure-Channel (PCh) SuperCritical Water-cooled Reactor (SCWR) concept, which is one of the six Generation-IV nuclear technologies, featuring two-pass (re-entrant) counter-flow fuel-channel assembly. This generic PCh SCWR contains 336 vertical pressure channels (pressure tubes) and has a thermal power of 2540 MWth. Coolant is light water, and its temperature varies within the range of 350-625°C at a pressure of about 25 MPa. The objective of this paper is to perform a onedimensional steady-state thermal-hydraulic analysis of the reentrant-channel design with different types of fuels, namely UO_2 and UN. The thermal-hydraulics analysis was conducted while the 78-element fuel-bundle design was chosen as the reference fuel bundle.
