Thermal Analysis of a Test Fuel Element for a Reactor with Supercritical Water
For a SCWR fuel qualification test, a test loop with supercritical pressure conditions is proposed to be installed in the LVR-15 research reactor in the Research Center (R)e(z). The active channel is built from four coaxial channels, which are consecutively passed through by the coolant. Four fuel rods, each with a length of 0.6 m and a diameter of 8 mm, are installed inside and heated with a fissile power of 53 kW in total. The thermo-hydraulic conditions at supercritical pressure inside the proposed geometry of the active channel have been investigated in a parametric study. Cross section averaged coolant temperatures have been predicted with a one-dimensional routine including heat transfer with neighbouring channels. Local coolant temperatures in the test section and fuel cladding surface temperatures have been analyzed with the CFD software STAR-CD. As exemplary results, we show temperatures for a mass flow rate of 0.14 kg/s, where the maximum cladding temperatures exceed the material limit, and for an increased mass flow of 0.24 kg/s with acceptable temperatures.
Fuel qualification test supercritical water cooled reactor thermal hydraulic analysis
M. Raqué A. Wank T. Schulenberg P. Hajek
Karlsruhe Institute of Technology D-76021 Karlsruhe, Germany Research Centre (R)e(z) Ltd. Husinec- (R)e(z) 130, 250 68 (R)e(z), Czech Republic
国际会议
上海
英文
1005-1016
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）