System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents

Y Jin, X Wu, K Shirvan - Nuclear Engineering and Design, 2020 - Elsevier
Abstract Following the Fukushima Daiichi nuclear accident in 2011, researches on Accident-
tolerant fuels (ATFs) are currently of high interest in not only the nuclear industry but also
governmental and international organizations. In this work, a quantitative evaluation of the
performance of monolithic FeCrAl cladding and Cr-coated Zircaloy cladding has been
performed for Pressurized Water Reactor (PWR) Station Blackout (SBO) accidents. A
generic PWR model has been built in system thermal-hydraulics code TRACE based on the …

System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents

X Wu, K Shirvan - Nuclear Engineering and Design, 2020 - Elsevier
Abstract Near-term Accident Tolerant Fuel (ATF) claddings, such as iron-chromium-
aluminum (FeCrAl) and chromium (Cr)-coating, are being extensively studied as candidates
to replace the current zircaloy claddings. They present excellent oxidation resistance in high-
temperature steam environment that has the potential to greatly reduce the hydrogen
production and increase coping time in Beyond Design Basis Accident (BDBA) scenarios. In
this work, since we are investigating unmitigated BDBA conditions, coping time is treated as …
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