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Argonne opens registration for D&D training course
Registration is open for Argonne National Laboratory’s Facility Decommissioning Training Course, a four-day instruction designed for those responsible for the decontamination and decommissioning of nuclear facilities and who are looking to understand the full breadth and depth of the D&D processes.
The next session will be held July 16–19 in Santa Fe, N.M. Information on the course and how to register can be found here.
Xingang Zhao, Koroush Shirvan, Yingwei Wu, Mujid S. Kazimi
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 553-567
Technical Paper | doi.org/10.13182/NT16-45
Articles are hosted by Taylor and Francis Online.
With the objective of providing long-term energy supply via actinide breeding and burning, the next-generation boiling water reactor (BWR) design, the Hitachi’s resource-renewable BWR (RBWR), has been proposed. Unlike a traditional square lattice BWR fuel bundle, the RBWR bundles are shorter with hexagonal tight lattice arrangement and heterogeneous axial fuel zoning. The RBWR’s different core geometry combined with the higher power-to-flow ratio and void fraction necessitates the reexamination of the standard BWR thermal-hydraulic models.
For the prediction of dryout, the previously derived best-estimate empirical correlation showed significant scatter when compared to experimental data within its calibration database. In this work, the correlation is further calibrated and improved by supplementing tight bundle data with relevant critical power data for tubes and annuli to better quantify the effects of various parameters and by incorporating subchannel-level results to account for intra-assembly flow mixing. Another approach using the mechanistic three-field model is also investigated, and the minimum critical power ratio of the RBWR design is evaluated.
For the prediction of void fraction, measurements and the three-field model in annular flow regime reveal that the common drift flux approaches tend to overestimate the void fraction at small hydraulic diameters. The void fraction dependence on hydraulic diameter below 10 mm requires further experimentation and high-fidelity mechanistic simulations.