A5011477428- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Engineering Applied Research
- Risk and Safety Analysis
- Combustion and Detonation Processes
- Heat Transfer and Boiling Studies
- Fluid Dynamics and Heat Transfer
- Graphite, nuclear technology, radiation studies
- Fluid Dynamics and Mixing
- Lattice Boltzmann Simulation Studies
- Computational Fluid Dynamics and Aerodynamics
- Spacecraft and Cryogenic Technologies
- Heat Transfer and Optimization
- Safety and Risk Management
- Fluid Dynamics Simulations and Interactions
- Heat transfer and supercritical fluids
- Fluid Dynamics and Turbulent Flows
- Vehicular Ad Hoc Networks (VANETs)
- Induction Heating and Inverter Technology
- Advanced Data Processing Techniques
- Vacuum and Plasma Arcs
- Thermal Analysis in Power Transmission
- Aerodynamics and Fluid Dynamics Research
- Fluid Dynamics and Thin Films
Korea Atomic Energy Research Institute
2012-2024
The thermal-hydraulic research supporting the development of an integral type reactor named System-integrated Modular Advanced ReacTor (SMART) is discussed. First, SMART program introduced. Standard Design Approval (SDA) for was certificated in 2012 based on extensive technical validation activities during 2009 to 2012, and a set passive safety systems (PSSs) designed validated 2013 2015 after Fukushima Daiichi accident. During 2016 2018, Kingdom Saudi Arabia Korea conducted 3-year project...
Many thermal–hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of SMART (System-integrated Modular Advanced ReacTor) design, standard design approval which was issued by Korean regulatory body. In this paper, contributions these to are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification Integral Simulation Transients and Accidents-Integral Test Loop) has utilized assess TASS/SMR-S (Transient Set-point...
To validate the performance and safety of an integral type reactor SMART, a thermal-hydraulic effect test facility, VISTA-ITL, is introduced with discussion its scientific design characteristics. The VISTA-ITL was used extensively to assess SMART design, especially for passive system such as residual heat removal system, various analysis codes. program includes several tests on SBLOCA, CLOF, PRHRS performances support verification contribute licensing by providing proper data validating A...
Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., SMART-ITL facility. The types of break are a system line break, shutdown cooling and pressurizer valve break. thermal–hydraulic phenomena show traditional behavior to decrease temperature pressure whereas local slightly different during early stage transient after simulation. A high-pressure...
Experiments on the heat transfer characteristics and natural circulation performance of passive residual removal system (PRHRS) for SMART-P have been performed by using high temperature/high pressure thermal-hydraulic test facility (VISTA). The VISTA consists primary loop, secondary PRHRS auxiliary systems to simulate SMART-P, a pilot plant SMART. loop is composed steam generator (SG) side, simulated core, main coolant pump, piping, SG exchanger, piping. PRHRS, exchangers emergency cooldown...
An innovative safety concept for a light water reactor has been developed at the Korea Atomic Energy Research Institute. It is unique that adopts both fast heat transfer mechanism small containment and changing of cooling geometry to take advantage potential, thermal, dynamic energies cold in containment. can bring about rapid long-term decay heat. By virtue this concept, nuclear fuel damage events be prevented. The ultimate contributes minimization exchanger size volume. A ensure...
A thermal-hydraulic integral effect test facility, SMART-ITL, was constructed to examine the system performance of SMART, a 330 MWt type reactor, and provide data for validation related models in analysis codes. SMART is equipped with various passive systems such as residual heat removal (PRHRS), safety injection (PSIS), an automatic depressurization (ADS). The PSIS made up four core makeup tanks (CMTs), (SITs), piping. Over 10 tests have been performed investigate behavior single train (a...
Even for small modular reactors (SMRs) with all large pipes removed, a small-break loss-of-coolant accident (SBLOCA) is an important design-basis (DBA). Experimental simulation of the SBLOCA scenario essential before prototype reactor realized. The system-integrated advanced (SMART) one SMRs developed by Korea Atomic Energy Research Institute. An integral test loop, SMART-ITL, was also constructed to carry out several types thermal-hydraulic effects tests reactor. SMART-ITL designed...
An integral effect test was successfully performed to provide data assess the capability of system analysis code simulate a complete loss reactor coolant (RCS) flow rate (CLOF) scenario for SMART (System-integrated Modular Advanced ReacTor) design. The steady-state conditions were achieved satisfy initial presented in requirement, its boundary accurately simulated, and CLOF design reproduced properly using VISTA-ITL facility. natural circulation RCS about 12.0% rated passive residual heat...