Characteristic of two-phase slanting flow in rod bundle.
スポンサーリンク
概要
著者
-
OSAKABE Masahiro
Japan Atomic Energy Research Institute
-
ADACHI Hiromichi
Japan Atomic Energy Research Institute
関連論文
- Simulation of PWR Turbine Trip Transient in ROSA-IV Large Scale Test Facility
- Heat Transfer Calculation of Simulated Heater Rods throughout Reflood Phase in Postulated PWR-LOCA Experiments
- Effects of partial flow blockage on core heat transfer in forced-feed reflood tests.
- Experimental study of upper core quench in PWR reflood phase.
- Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF.
- Interfacial drag coefficient of air-water mixture in rod bundle.
- Characteristic of two-phase slanting flow in rod bundle.
- Two-phase flow pattern and heat transfer during core uncovery.
- Analysis of saturated film boiling heat transfer in reflood phase of PWR-LOCA. Turbulent boundary layer model.:Turbulent Boundary Layer Model
- Initial thermal-hydraulic behaviors under simultaneous ECC water injection into cold leg and upper plenum in a PWR-LOCA.
- Air-Water Two-Phase Cross Flow Resistance in Rod Bundle
- Experimental study of two-dimensional thermal-hydraulic behavior in core during reflood phase of PWR LOCA.