Effect of PVD-coated chromium on the subcooled flow boiling performance of nuclear reactor cladding materials
Author(s)
Seong, Jee Hyun; Wang, Chi; Phillips, Bren; Bucci, Matteo
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Show full item recordDate issued
2022Department
Massachusetts Institute of Technology. Department of Nuclear Science and EngineeringJournal
Applied Thermal Engineering
Publisher
Elsevier BV
Citation
Seong, Jee Hyun, Wang, Chi, Phillips, Bren and Bucci, Matteo. 2022. "Effect of PVD-coated chromium on the subcooled flow boiling performance of nuclear reactor cladding materials." Applied Thermal Engineering, 213.
Version: Author's final manuscript