Core liquid level depression due to manometric effect during PWR small break LOCA. Effect of break area.:Effect of Break Area
スポンサーリンク
概要
- 論文の詳細を見る
The 10, 5 and 2.5% cold leg break loss-of-coolant accident experiments were conducted by using the Large Scale Test Facility (LSTF) of the Rig of Safety Assessment (ROSA)-IV program. In the early stage of the 5% break experiment, the core collapsed liquid level was depressed nearly to the core bottom and the dryout of the core was observed. However, the core liquid level depression without the core dryout was observed in the 10 and 2.5% break experiments. In the three break experiments, the core liquid levels were recovered just after the loop seal clearing. <BR>The manometric effect due to the liquid seal formation in the loop seal and the liquid holdup in the steam generator (SG) U-tubes upflow-side caused a depression of the core collapsed liquid level. The liquid holdup in the U-tubes upflow-side was observed after the termination of the two-phase circulation due to the phase separation at the U-tubes top. The counter current flow limiting (CCFL) and the condensation of steam was considered to be the main reason for the liquid holdup. In the 10, 5 and 2.5% break experiments, the termination of the two-phase circulation and the loop seal clearing were observed approximately at 4060% and 30% mass inventory in the primary system, respectively.
- 一般社団法人 日本原子力学会の論文
著者
-
TASAKA Kanji
Japan Atomic Energy Research Institute
-
KAWAJI Masahiro
Japan Atomic Energy Research Institute
関連論文
- Simulation of PWR Turbine Trip Transient in ROSA-IV Large Scale Test Facility
- Simulation Test of PWR Instrument Tube Break LOCA in ROSA-IV Program
- Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF.
- Simulation experiment of five percent small break loss-of-coolant accident of boiling water reactor.
- Interfacial drag coefficient of air-water mixture in rod bundle.
- Two-phase flow pattern and heat transfer during core uncovery.
- Investigation of pre- and post-dryout heat transfer in upward steam-water two-phase flow at low flow rate.
- Simplified method for calculation of neutron capture transformation effects of fission products on decay power.
- Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.
- Core liquid level depression due to manometric effect during PWR small break LOCA. Effect of break area.:Effect of Break Area