Simulation of PWR Turbine Trip Transient in ROSA-IV Large Scale Test Facility

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概要

• 論文の詳細を見る
• 一般社団法人 日本原子力学会の論文

著者

• Kukita Yutaka

  Japan Atomic Energy Research Institute

• TASAKA Kanji

  Japan Atomic Energy Research Institute

• KOIZUMI Yasuo

  Japan Atomic Energy Research Institute

• TANAKA Mitsugu

  Japan Atomic Energy Research Institute

• OSAKABE Masahiro

  Japan Atomic Energy Research Institute

• OTSUKI Masato

  Japan Atomic Energy Research Institute

• KAWAJI Masahiro

  Japan Atomic Energy Research Institute

関連論文

• ROSA/AP600 Testing : Facility Modifications and Initial Test Results
• Intentional Depressurization of Steam Generator Secondary Side during a PWR Small-Break Loss-Coolant Accident
• Sub- to Supercritical Flow Transition in a Horizontally-Stratified Two-Phase Flow in PWR Hot Legs
• The Simulation Test to Start up the PIUS-Type Reactor from Isothermal Fluid Condition
• Analysis of System Thermal Hydraulic Responses for Passive Safety Injection Experiment at ROSA-IV/Large Scale Test Facility. Using JAERI Modified Version of RELAP5/MOD2 Code.:Using JAERI Modified Version of RELAP5/MOD2 Code
• 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
• Simulation Test of PWR Instrument Tube Break LOCA in ROSA-IV Program
• 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.
• 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.
• 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
• 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

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