Simulation Test of PWR Instrument Tube Break LOCA in ROSA-IV Program
スポンサーリンク
概要
- 論文の詳細を見る
A small loss-of-coolant accident (LOCA) test was conducted simulating a PWR instrument tube break as one of the break location parameter tests in the ROSA-IV large scale test facility (LSTF). Similarities and differences are studied experimentally between the test and a cold leg break (CLB) LOCA test.
- 一般社団法人 日本原子力学会の論文
著者
-
SUZUKI Mitsuhiro
Japan Atomic Energy Agency
-
SUZUKI Mitsuhiro
Japan Atomic Energy Research Institute
-
TASAKA Kanji
Japan Atomic Energy Research Institute
関連論文
- Reliability of Core Exit Thermocouple for Accident Management Action during SBLOCA and Abnormal Transient Tests at ROSA/LSTF
- Performance of Core Exit Thermocouple for PWR Accident Management Action in Vessel Top Break LOCA Simulation Experiment at OECD/NEA ROSA Project
- 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