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Westinghouse teams with Nordion and PSEG to produce Co-60 at Salem
Westinghouse Electric Company, Nordion, and PSEG Nuclear announced on Tuesday the signing of long-term agreements to establish the first commercial-scale production of cobalt-60 in a U.S. nuclear reactor. Under the agreements, the companies are to apply newly developed production technology for pressurized water reactors to produce Co-60 at PSEG’s Salem nuclear power plant in New Jersey.
Trevor Melsheimer, Craig Menezes, Yassin A. Hassan
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 725-741
Research Article | doi.org/10.1080/00295450.2024.2348853
Articles are hosted by Taylor and Francis Online.
Flow blockages in Liquid Metal Fast Reactor (LMFR) fuel assemblies that can cause fuel pin cladding failures require further investigation for the development and optimization of these Generation IV reactor designs. The objective of this study was to experimentally evaluate the effects of a porous blockage accident scenario on laminar flow behavior in the interior subchannels of a prototypical 61-pin wire-wrapped rod bundle. The laminar flow condition is considered because of its importance to natural circulation and loss-of-coolant-accident operating scenarios as well as the limited availability of experimental data. The matched-index-of-refraction method was utilized to obtain two-dimension two-component time-resolved particle image velocimetry (TR-PIV) measurements at three planes centered on blocked and neighboring subchannel regions. Time-averaged first-order and second-order statistics, computed by Reynolds decomposition, were visualized including the mean and fluctuating streamwise and spanwise velocity components. Line profiles described the evolution of flow from upstream regions, to separated flow, and recombination downstream, while a modified Galilean decomposition distinguished differences between flow in the blocked measurement plane and flow in its neighboring counterpart region. Spatial-temporal cross-correlations were performed for the streamwise velocity fluctuations to characterize the convection velocity and decay of traveling vortices in the wake of the porous blockage. The isothermal TR-PIV measurements from this study provide high-fidelity experimental data sets for the validation of computational models and numerical studies to characterize complex fluid phenomena in wire-wrapped rod bundles during the potential accident scenario of a porous, interior flow blockage.