Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor |
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| Affiliation: | 1. Department of Mechanical Engineering, Texas A&M University, 3123 TAMU, College Station, TX 77843, USA;2. Department of Nuclear Engineering, Texas A&M University, 3133 TAMU, College Station, TX 77843, USA;1. DICI - Università di Pisa, L.go Lucio Lazzarino n. 2, 56122 Pisa, Italy;2. ENEA, C.R. Brasimone, 40032 Camugnano BO, Italy;3. ENEA, C.R. Frascati, 00044 Frascati RM, Italy;4. DIAEE – Nuclear Section, “Sapienza” Università di Roma, 00186 Roma, Italy;5. GRS, Cooling Circuit Department Reactor Safety Research Division, Garching, Germany;6. ENEA, C.R. Bologna, Via Martiri di Monte Sole n. 4, 40129 Bologna, Italy;1. Nuclear Research Center of Birine, Algeria;2. University of Pisa, Italy;3. University of Science and Technology Houari Boumediène, Algeria;1. Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210, USA;2. University of Idaho, Idaho Falls, ID 83401, USA;3. Idaho National Laboratory, Idaho Falls, ID 83415, USA;1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, PR China;2. School of Aerospace, Mechanical & Manufacturing Engineering, RMIT University, Melbourne, VIC 3083, Australia |
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| Abstract: | The Very High Temperature Reactor (VHTR) is a Generation IV nuclear reactor that is currently under design. During the design process multiple studies have been performed to develop safety codes for the reactor. Two major accidents of interest are the Pressurized Conduction Cooldown (PCC), and the Depressurized Conduction Cooldown (DCC) scenario. Both involve loss of forced coolant to the core, except the latter involves a pressure loss in the main coolant loop. During normal operation a circulator pumps the coolant into the upper plenum and down through the core, but following a loss of forced coolant the natural convection causes the flow to reverse to go through the core into the upper plenum. Computer codes may be developed to simulate the phenomenon that occurs in a PCC or DCC scenario, but benchmark data is needed to validate the simulations; previously there were no experimental test facilities to provide this. This study will cover the design, construction, and preliminary testing of a 1/16th scaled model of a VHTR that uses Particle Image Velocimetry (PIV) for flow visualization in the upper plenum. Three tests were run for a partially heated core at statistically steady state, and PIV was used to generate the velocity field of three naturally convective adjacent jets; the turbulent mixing of the jets was observed. After performing a sensitivity analysis the flow rate of a single pipe was extracted from the PIV flow field, and compared with an ultrasonic flowmeter and analytic flow rate. All the values lied within the uncertainty ranges, validating the test results. |
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| Keywords: | Natural convection Particle image velocimetry VHTR Pressurized conduction cooldown Depressurized conduction cooldown Upper plenum |
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