A Large Scale Three-Dimensional Simulation on Thermal-Hydraulics of Supercritical Pressure Water in a Fuel Bundle for SCWR
1 Japan Atomic Energy Agency, Tokai-mura, Ibarak-keni, 319-1195, Japan
2 Yamato System Engineer, Hitachi-shi, Ibarak-keni, 317-0063, Japan
* Kazuyuki Takase, firstname.lastname@example.org
Development of a numerical analysis method was performed to clarify thermal-hydraulic characteristics in supercritical water reactors. Because the thermo-physical property of fluids at the supercritical pressure condition is different from that at the subcritical condition and has a special feature, current numerical analysis codes cannot be applied. Then, Japan Atomic Energy Agency is developing a numerical analysis code which can calculate the thermo-fluid properties of the supercritical fluids correctly. This paper describes the predicted results of a newly developed analysis code and the comparison results with the experimental results.
Key words: Thermal-Hydraulics / Numerical Analysis / Supercritical Pressure Water / Fuel Bundle / Complex Geometry
© Owned by the authors, published by EDP Sciences, 2014