Critical heat flux on zircaloy and accident tolerant fuel cladding under prototypical conditions of pressurized and boiling water reactors

نویسندگان

چکیده

First of a kind high spatial and temporal resolution temperature measurements Pressurized Water Reactor Boiling simulated fuel pins (high heat flux cosine profile heaters) in annular rod type geometry during nucleate boiling, departure from boiling re-wetting has been performed. Distributed fiber optic the cladding axial with resolutions down to 2.5 mm axially at up three equally spaced azimuthal locations per have demonstrated similarities differences different accident tolerant materials. These experiments show performance precise measurement location evolution dryout followed by phenomena (see supplementary time history critical event). Experimental parameters varied coolant mass fluxes 1695 2712 kg/m2s, pressures 10 20 MPa, inlet subcooling 55 °C. It was found that coatings material little effect on value flux. Any discrepancies between local verified among are attributed captured experiment high-resolution optical data. Substantial survive event were however observed post-test X-ray inspection. External evident damage internal cracks pin having bare zircaloy regions associated occurrence for longer periods. Such damages zirconium oxidation, not noticed Cr coated or FeCrAl claddings. results indicate use as may increase survivability short transients.

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ژورنال

عنوان ژورنال: Applied Thermal Engineering

سال: 2022

ISSN: ['1873-5606', '1359-4311']

DOI: https://doi.org/10.1016/j.applthermaleng.2022.118740