Countercurrent Gas-Liquid Flow in Boiling Channels
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1986.9735012
Reference28 articles.
1. BWR Loss of Coolant Integral Tests with Two Bundle Loop, (I) Thermal-Hydraulic Characteristics in Parallel Channels
2. BWR LOSS of Coolant Integral Tests with Two Bundle Loop, (II) Effect of ECCS Activation Modes on Thermal-Hydraulic Characteristics
3. Speyer, D. M. and Kmetyk, L. 1977.“Nuclear Reactor Safety Heat Transfer”55ASME.
4. Countercurrent gas-liquid flow in parallel vertical tubes
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