An experimental investigation of the structural response of reactor fuel plates

MITR Low-Enriched Uranium Conversion Fluid-Structure Interaction Preliminary Design Verification

“…In the early 1990s, Swinson et al conducted flow tests on involute plate assemblies in support of the Advanced Neutron Source reactor design [14], [15], [16], [17]. To lower the flow velocity and pressure required for the anticipated collapse conditions, the test assemblies were made from epoxy.…”

“…16 to Figure4.20 are calculated using fluid properties at 25℃ for the purpose of showing distribution and convergence trends only.…”

“…16 shows a typical von Mises stress distribution on the top of the plate. This figure presents the stresses for Case 1 with the nominal geometry and flow conditions.ANL/RTR/TM-21/Low-Enriched Uranium Conversion Fluid-Structure Interaction Preliminary Design Verification 48…”

Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel

“…Flow tests measuring thermal characteristics of the fuel plates were performed that were designed to measure the heat transfer capabilities of the design [104][105][106][107]. Another set of experiments were performed to test the deflection caused by the pressure differentials from the coolant flow [101,63,102,59,103,108,109,110].…”

Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design

“…In the early 1990s Swinson, et al conducted flow tests on involute plate assemblies in support of the Advanced Neutron Source reactor design [17], [18], [19], [20]. To lower the flow velocity and pressure required for the anticipated collapse conditions, the test assemblies were constructed of epoxy.…”