A5007024182- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Heat transfer and supercritical fluids
- Fluid Dynamics Simulations and Interactions
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Fluid Dynamics and Heat Transfer
- Subcritical and Supercritical Water Processes
- Graphite, nuclear technology, radiation studies
- Lattice Boltzmann Simulation Studies
- High-Velocity Impact and Material Behavior
- Nuclear Physics and Applications
- Metallurgical Processes and Thermodynamics
- Advanced ceramic materials synthesis
- Numerical methods in engineering
- Risk and Safety Analysis
- Radioactive contamination and transfer
- Fusion materials and technologies
- Non-Destructive Testing Techniques
- Aluminum Alloy Microstructure Properties
- Solidification and crystal growth phenomena
- Advanced Combustion Engine Technologies
- Spacecraft and Cryogenic Technologies
- Geotechnical Engineering and Underground Structures
- Thermochemical Biomass Conversion Processes
Waseda University
2015-2024
Organisation de Coopération et de Développement Economiques
2012-2015
Nuclear Energy Agency
2014
Japan Atomic Energy Agency
2009-2012
The University of Tokyo
2002-2010
Hiroshima University
1996
Summary The Lagrangian moving particle semi‐implicit (MPS) method has potential to simulate free‐surface and multiphase flows. However, the chaotic distribution of particles can decrease accuracy reliability in conventional MPS method. In this study, a new Laplacian model is proposed by removing errors associated with first‐order partial derivatives based on corrected matrix. Therefore, corrective matrix applied all discretization models enhance computational accuracy. Then, developed are...
Liquid ZrO2 is one of the most important materials involved in severe accident analysis a light-water reactor. Despite its importance, physical properties liquid are scarcely reported. In particular, there no experimental reports on viscosity ZrO2. This mainly due to technical difficulties measurement thermo-physical ZrO2, which has an extremely high melting point. To address this problem, aerodynamic levitation technique was used study. The density calculated from mass and volume, estimated...
The equilibrium core of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H) is designed by three-dimensional neutronic and thermal-hydraulic coupled calculations. average coolant outlet temperature 500°C accurately evaluated for first time in development SCLWR-H. one key parameters, which must be determined order to establish concept this unique reactor design. However, it can only design method, taking into account control rod patterns, fuel loading coupling...
Summary Corrective matrix that is derived to restore consistency of discretization schemes can significantly enhance accuracy for the inside particles in Moving Particle Semi‐implicit method. In this situation, error due free surface and wall boundaries becomes dominant. Based on recent study Neumann boundary condition (Matsunaga et al, CMAME, 2020), corrective MPS are generalized straightforwardly accurately impose condition. However, new still easily trigger instability at because biased...
Modeling the boiling phase change is particularly challenging for Lagrangian particle methods due to a high density ratio and dramatic volume expansion. In this study, incompressible moving semi-implicit (MPS) method weakly compressible smoothed hydrodynamics (SPH) are coupled develop an incompressible–compressible modeling multiphase flow with boiling. The coupling strategies developed by Lind et al. (JCP, 2016) adopted. A speed of sound must be employed in SPH bubbles heavy liquid under...
An equilibrium core for the High Temperature Supercritical-pressure Light Water Reactor, now called Super Reactor (Super LWR), has been designed. The fuel assemblies loaded in peripheral region of are cooled with descending flow to achieve a high average coolant outlet temperature. This scheme is compatible low leakage loading pattern (LLLP) which 3rd cycle region. Stainless steel used rod claddings and structural materials. Watts correlations predicting heat transfer core. They take into...
This paper describes safety analysis of the high-temperature supercritical water-cooled thermal reactor with downward-flow water rods (called Super LWR) at pressure. Eleven transients and four accidents are chosen for considering types abnormalities. The cladding temperature is taken as important transient criterion instead heat flux ratio. once-through cooling system rod characterize LWR. "Loss feedwater" because it same "loss coolant flow" unlike BWR PWR. However, mitigate core heat-up...
Abstract This paper describes design concept of safety system the high-temperature supercritical pressure light water cooled reactor with downward-flow rods (Super LWR). Since this is once-through cooling without level and coolant circulation, fundamental requirement keeping core flow rate while that reactors (LWR) inventory. "Coolant supply from cold-leg" "coolant outlet at hot-leg" are needed for it. The advantage depressurization induces cools core. rod enhances effect because top dome...
Spreading of molten core (corium) on reactor containment vessel floor and corium-concrete interaction (MCCI) are important phenomena in the late phase a severe accident for assessment integrity managing accident. The research at Waseda University has been advancing to show that simulations with moving particle semi-implicit (MPS) method (one methods) can greatly improve analytical capability mechanical understanding melt behavior accidents. MPS models have developed verified regarding...