TY - GEN
T1 - Fuel performance of multi-layered zirconium based accident tolerant fuel cladding
AU - Wagih, Malik
AU - Che, Yifeng
AU - Shirvan, Koroush
N1 - Funding Information:
The support for this work was provided by US Department of Energy Integrated Research Project Grant: DE-NE0008416.
PY - 2017
Y1 - 2017
N2 - The Fukushima and Three Mile Island severe accidents highlighted the weakness of uranium-dioxide and zirconium based cladding system (UO2-Zr). The Accident Tolerant Fuel program is mainly focused at extending the time for fuel failure during postulated severe accident compared to UO2-Zr. This paper overviews the feasibility of multi-layered Zirconiumbased cladding concepts from the fuel performance pointof-view. The multi-physics fuel performance tool, MOOSE/BISON is utilized to simulate different Zirconium-based alloys with a thin layer of Chromium (Cr) or thin layer of FeCrAl alloy with a thin Molybdenum (Mo) interlayer to prevent Iron diffusion into Zirconium. The preliminary simulations found that a ∼50 μm thick layer on outside of Zirconium will undergo plasticity under normal operation due to difference in thermal expansion and swelling among the different materials. Additional experimental work is currently underway to further validate the multi-layered cladding structural models at normal and postulated severe accident conditions.
AB - The Fukushima and Three Mile Island severe accidents highlighted the weakness of uranium-dioxide and zirconium based cladding system (UO2-Zr). The Accident Tolerant Fuel program is mainly focused at extending the time for fuel failure during postulated severe accident compared to UO2-Zr. This paper overviews the feasibility of multi-layered Zirconiumbased cladding concepts from the fuel performance pointof-view. The multi-physics fuel performance tool, MOOSE/BISON is utilized to simulate different Zirconium-based alloys with a thin layer of Chromium (Cr) or thin layer of FeCrAl alloy with a thin Molybdenum (Mo) interlayer to prevent Iron diffusion into Zirconium. The preliminary simulations found that a ∼50 μm thick layer on outside of Zirconium will undergo plasticity under normal operation due to difference in thermal expansion and swelling among the different materials. Additional experimental work is currently underway to further validate the multi-layered cladding structural models at normal and postulated severe accident conditions.
UR - https://www.scopus.com/pages/publications/85036472755
M3 - Conference contribution
AN - SCOPUS:85036472755
T3 - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
BT - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PB - International Congress on Advances in Nuclear Power Plants, ICAPP
T2 - 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Y2 - 24 April 2017 through 28 April 2017
ER -