Two-Phase Flow Modeling of Critical Heat Flux for Subcooled and Low-Quality Flow Boiling

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 348
  • Download : 0
Issue Date
1998
Language
ENG
Citation

The 1st Korea-Japan Symposium on Nuclear Thermal Hydaulics and Safety

URI
http://hdl.handle.net/10203/123240
Appears in Collection
NE-Conference Papers(학술회의논문)
Files in This Item
There are no files associated with this item.

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0