Air-Water Two-Phase Cross Flow Resistance in Rod Bundle
スポンサーリンク
概要
著者
-
Iwamura Takamichi
Japan Atomic Energy Agency
-
SOBAJIMA Makoto
Japan Atomic Energy Research Institute
-
ADACHI Hiromichi
Japan Atomic Energy Research Institute
関連論文
- Transport Mechanism of Thermohydraulic Instability in Natural Circulation Boiling Water Reactors during Startup
- ICONE11-36099 CRITICAL POWER CHARACTERISTICS OF TIGHT LATTICE BUNDLES
- A Concept of Passive Safety Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal
- ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT
- Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
- Application of PSA Methodology to Design Improvement of JAERI Passive Safety Reactor(JPSR)
- Transient Analysis for Design of Primary Coolant Pump Adopted to JAERI Passive Safety Reactor JPSR
- Evaluation on Driving Force of Natural Circulation in Downcomer for Passive Residual Heat Removal System in JAERI Passive Safety Reactor JPSR
- CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution.
- Burnout characteristics under flow reduction condition.
- Characteristic of two-phase slanting flow in rod bundle.
- 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.
- Experimental modeling of steam-water countercurrent flow limit for perforated plates.