Abstract
Experimental studies on thermal and hydraulic performance of a fuel stack of the VHTR(Very High-temperature Gas-cooled Reactor) have been performed with the fuel stack test section (T1) of the Helium Engineering Demonstration Loop (HENDEL) at JAERI, using helium gas of opera-tional condition of the VHTR. This report describes test results obtained by single-channel test rig of T1. Tests were perormed with inlet temperature of 20350°C inlet pressure of 0.4-4.0 MPa and inlet Reynolds number of 80023, 000. A simulated fuel rod has uniform heat flux distribution in the axial direction and was heated up to maximum power of 90 kW. The conclusions derived from the tests were that friction factors and heat transfer coefficients were about 20% and 1560% higher than those for a concentric smooth annulus to the region of Re>2, 000, respectively. The reason may be due to the effect of spacer ribs on the outer surface of the simulated fuel rod.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
More From: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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.