Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses
スポンサーリンク
概要
- 論文の詳細を見る
The effectiveness of an operator-initiated steam generator (SG) secondary-side depressurization on the core cooling performance during small-break loss of coolant accidents (SBLOCAs) in a pressurized water reactor (PWR) with total failure of the high pressure injection (HPI) systems is studied. The study is based on experiments conducted in the ROSA-V Large Scale Test Facility (LSTF) and analyses with the RELAP5/Mod3 code. The sensitivity of the core minimum liquid level and peak cladding temperature (PCT) to the secondary-side depressurization rate and the initiation time of the depressurization is evaluated analytically for various break sizes. It is shown that the PCT takes a maximum value for break areas between 1.0% and 1.5% of the cold leg cross-sectional area. The conditions which the depressurization rate and the initiation time should satisfy to limit the maximum PCT are derived.
- 社団法人 日本原子力学会の論文
- 1998-12-25
著者
-
KUKITA Yutaka
Department of Energy Engineering and Science, Nagoya University
-
Kukita Yutaka
Department Of Energy Engineering And Science Nagoya University
-
Kukita Y
Department Of Energy Engineering And Science Nagoya University
-
Kukita Yutaka
Nagoya University
-
ASAKA Hideaki
Japan Atomic Energy Research Institute
-
ANODA Yoshinari
Japan Atomic Energy Research Institute
-
Asaka H
Japan Atomic Energy Research Institute
-
Ohtsu Iwao
Japan Atomic Energy Research Institute
関連論文
- Development of an Advanced Startup Procedure for a PIUS-type Reactor
- Recoupling and Decoupling of Parallel Loops in Simulated PIUS-type Reactor Shutdown and Restart Transients
- Dynamic Response of Hot/Cold Liquid Interfaces to Pump Speed Perturbations in a Thermal-Hydraulic Loop Simulating a PIUS-type Reactor
- ICONE11-36609 Steady Streaming Associated with Forced Oscillation of Overlaid Immiscible Fluids
- ICONE11-36525 Macroscopic Streaming Associated with Standing Internal Wave
- Interface Waves Excited by Vertical Vibration of Stratified Fluids in a Circular Cylinder
- ICONE11-36298 SYSTEM PRESSURE EFFECT ON DENSITTY-WAVE INSTABILITY : SIMPLIFIED MODEL ANALYSIS AND EXPERIMENTS
- ROSA/AP600 Testing : Facility Modifications and Initial Test Results
- Small-scale Experiment on Subcooled Water Jet Injection into Molten Alloy by Using Fluid Temperature-Phase Coupled Measurement and Visualization
- ANALYSIS OF FREE-SURFACE INSTABILITY ON LIQUID JET WITH DIFFERENT LEVELS OF SIMPLIFICATION OF VELOCITY PROFILE(Liquid Flow)
- Internal-Shear Mode Instabilities on High-Speed Liquid Jet, (II) : Experimental Analysis of Curved Target Flow
- Internal-Shear Mode Instabilities on High-Speed Liquid Jet, (I) : Characteristics of Linear Solutions
- Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses
- Core Liquid Level Responses Due to Secondary-Side Depressurization during PWR Small Break LOCA
- Intentional Depressurization of Steam Generator Secondary Side during a PWR Small-Break Loss-Coolant Accident
- ICONE11-36288 OPTICAL MEASUREMENT OF WAVES ON HIGH-SPEED LITHIUM JET SIMULATING IFMIF TARGET FLOW
- In-pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-boiling Heat Transfer
- Interfacial Friction Factor for High-Pressure Steam/Water Stratified-Wavy Flow in Horizontal Pipe
- Water Flow Simulation Test on Flow-Induced Oscillation of Thermowell in Prototype Fast Breeder Reactor "MONJU"
- Sub- to Supercritical Flow Transition in a Horizontally-Stratified Two-Phase Flow in PWR Hot Legs
- ICONE11-36146 WATER FLOW EXPERIMENTS AND ANALYSES ON THE CROSS-FLOW TYPE MERCURY TARGET WITH PERFORATED PLATES
- S0802-4-5 配管減肉におけるオリフィス下流の物質伝達率計測(原子力システムおよび要素技術(4))
- Study on the Non-axisymmetric Flow between Two Parallel Rotating Disks
- Interface Behavior between Two Fluids Vertically Oscillated in a Circular Cylinder under Nonlinear Contact Line Condition : (1st Report, Measurement and Modeling of the Contact Line Behavior)
- 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
- Investigation of effect of pressure control system on BWR LOCA phenomena using ROSA-III test facility.
- 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.