[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security - Flowsheet Study of a Multistage Flash Desalination System for Cogeneration With High Temperature Gas-Cooled Reactor
Kamiji, Yu, Noguchi, Hiroki, Terada, Atsuhiko, Yan, XingYear:
2014
Language:
english
DOI:
10.1115/icone22-30142
File:
PDF, 1.34 MB
english, 2014