A5009176784- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Risk and Safety Analysis
- Combustion and Detonation Processes
- Nuclear and radioactivity studies
- Fluid Dynamics and Mixing
- Particle Dynamics in Fluid Flows
- Thermodynamic and Structural Properties of Metals and Alloys
- Heat Transfer and Boiling Studies
- Probabilistic and Robust Engineering Design
- Metallurgical Processes and Thermodynamics
- Heat transfer and supercritical fluids
- Graphite, nuclear technology, radiation studies
- Cyclone Separators and Fluid Dynamics
- Computational Fluid Dynamics and Aerodynamics
- Fluid Dynamics and Turbulent Flows
- Hydraulic and Pneumatic Systems
- Fault Detection and Control Systems
- Lattice Boltzmann Simulation Studies
- Fusion materials and technologies
- Fluid Dynamics and Heat Transfer
- Fluid Dynamics Simulations and Interactions
- Nuclear Physics and Applications
- Granular flow and fluidized beds
KTH Royal Institute of Technology
2016-2025
AlbaNova
2008-2019
Swedish Nuclear Fuel and Waste Management (Sweden)
2017
In engineering systems operating under high Schmidt (Sc) or Prandtl (Pr) number flow conditions, the demand for near-wall mesh refinement increases significantly, underscoring need cost-effective modeling approaches that avoid additional computational overhead. Existing models, which are predominantly designed low-Sc flows, overlook temporal filtering effects, resulting in inaccuracies theoretical description and mass transfer predictions. This paper addresses impact of Sc Pr by refining...
Characteristics of corium debris beds formed in a severe core melt accident are studied the Debris Bed Formation-Snapshot (DEFOR-S) test campaign, which superheated binary-oxidic melts (both eutectic and noneutectic compositions) as simulants discharged into water pool. Water subcooling pool depth found to significantly influence fragments' morphology agglomeration. When particle agglomeration is absent, tests produced with porosity ~60 70%. This higher than ~40% broadly used contemporary...
Direct contact condensation (DCC) of steam in the pressure suppression pool (PSP) is used to control containment Boiling Water Reactors (BWRs) and Advanced Pressurized (APWRs). The competition between momentum heat sources induced by injection through multi-hole spargers blowdown pipes determines whether thermally stratified or mixed. Development thermal stratification affects capacity PSP condense steam. To enable computationally efficient modeling transients, Effective Heat Source (EHS)...
Steam venting and condensation in a large pool of water can lead to either thermal stratification or mixing. In pressure suppression (PSP) boiling reactor (BWR), consistent mixing maximizes the capacity while development reduce steam which turn increase containment thereafter consequences be severe. Advanced modeling simulation direct contact systems remain challenge as evident commercial research codes mainly due small time-steps necessary resolve long transients. this work, effective...
The Effective Heat Source (EHS) and Momentum (EMS) models have been proposed to predict the development of thermal stratification mixing during a steam injection into large pool water. These effective are implemented in GOTHIC software validated against POOLEX STB-20 STB-21 tests PPOOLEX MIX-01 test. First, EHS model is test which shows stratification. Different numerical schemes grid resolutions tested. A<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"...