Effect of PVD-coated chromium on the subcooled flow boiling performance of nuclear reactor cladding materials
Name
ATF_R2_clean.pdf
Description
Accepted version
Size
1.55 MB
Format
Adobe PDF
Checksum (MD5)
41387452c359236218e962c51d951b90
Author(s)
Seong, Jee Hyun
Wang, Chi
Phillips, Bren
Bucci, Matteo
Date Issued
2022
Journal
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
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-NonCommercial-NoDerivs License
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1016/J.APPLTHERMALENG.2022.118670
