... Abstract Subchannel analysis, as a common tool utilized in nuclear reactor core thermal-hydraulic calculation, is essential to establish high-fidelity high-resolution reactor core simulator which shows growing potential in nuclear reactor operation and monitoring. However, thermal-hydraulic...

... is validated through Hassan 5 × 5 Particle Image Velocimetry experiment and PSBT benchmark. Numerical results demonstrate that SAPRE has large advantages in accurate prediction of local T/H parameters in rod bundles, which is of significance to safety and economy of PWR. subchannel analysis lateral...

... accident. Due to the asymmetric layout of fuel rods by the inner duct, it is necessary to estimate the temperature distribution to confirm feasibility of FAIDUS. In JAEA, an in-house subchannel analysis code named ASFRE has been developed as a FA design tool. For the typical FAs, the numerical results...

... the thermal hydraulic performance of the fuel assembly in NHR core. The thermal hydraulic performance of the fuel assembly is mainly analyzed by the subchannel analysis code which can accurately calculate the two-phase parameters. Therefore, this research employs subchannel analysis code COBRA-TF to simulate...

... discretization subchannel analysis isokinetic and non-isokinetic sampling cross-flow mixing Distribution of thermal and mass flow rate parameters of coolant in the cross-section of 7-rod bundle consisting of the tubes of 6.0-mm outside diameter and 1.0-m heated length for two types...

... to the cross flow was found in the experiment. The subchannel analysis code, ASFRE, was applied to the experimental analyses. Measured axial and transverse temperature distributions in the subassembly were correlated with the cross flow and the wire spacer. The calculated temperature profiles were in good...