Experimental study of SRT scrubbing model in water coolant pool

Planning Near-Term Tasks for the Development of Advanced Reactor Mechanistic Source Term Modeling and Simulation Tools

“…The first task centers on the completion of NEUP experiments at the University of Wisconsin regarding radionuclide bubble transport in sodium [12] and subsequent analysis of the results. Preliminary results, utilizing a water-loop, have already been published [13], with results from the sodium loop expected later this calendar year. Benchmark exercises utilizing the results are being prepared as part of an MST code comparison task under the Civil Nuclear Energy Research and Development Working Group (CNWG) with Japan [14].…”

The Release of the Simplified Radionuclide Transport (SRT) Code (V.2.1)

“…Additional information on the calculation performed by the detailed bubble model can be found in refs [9,10]. There have been recent improvements to the detailed bubble transport model and validation case based on findings from sodium bubble transport experiments conducted at the University of Wisconsin (UW) [11,12]. Multiple options are now available to users of the detailed bubble model, including the possibility to conduct an internal uncertainty analysis focused on the bubble transport calculation, which is performed separately from the code's greater uncertainty iterations, described in Section 2.2.2.…”

“…Past Argonne studies have noted the importance of this phenomenon, which has led to DOE:NE funding a series of experiments examining the phenomenon at the UW [11,12]. These experiments (further discussed in Section 4.1) provided valuable insight into the behavior of aerosols within bubbles in a sodium pool.…”

A Pathway for the Development of Advanced Reactor Mechanistic Source Term Modeling and Simulation Capabilities

“…These efforts, taking place at the University of Wisconsin and University of New Mexico, are scheduled to conclude within the next year. Validation efforts utilizing the experimental results have already begun [53] and will continue as the experiments complete. In addition, the validation efforts also form the basis of an international benchmark exercise with Japan as part of the Civil Nuclear Energy Research and Development Working Group (CNWG).…”