A5040255240- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Radiation Therapy and Dosimetry
- Nuclear Physics and Applications
- Advanced Radiotherapy Techniques
- Granular flow and fluidized beds
- Nuclear Engineering Thermal-Hydraulics
- Probabilistic and Robust Engineering Design
- Radiation Detection and Scintillator Technologies
- Medical Imaging Techniques and Applications
- Advanced Numerical Methods in Computational Mathematics
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Heat and Mass Transfer in Porous Media
- Radiomics and Machine Learning in Medical Imaging
- Fluid Dynamics and Mixing
- Thermochemical Biomass Conversion Processes
- Heat Transfer and Boiling Studies
- Iron and Steelmaking Processes
- Model Reduction and Neural Networks
- Particle Dynamics in Fluid Flows
- Heat transfer and supercritical fluids
- Fusion materials and technologies
- Fluid Dynamics and Heat Transfer
- Computational Fluid Dynamics and Aerodynamics
Delft University of Technology
2016-2025
Leiden University Medical Center
2023
Instituut voor Tropische Geneeskunde
2011
Budapest University of Technology and Economics
2006
Jet Propulsion Laboratory
2000-2001
Applied Technologies (United States)
2001
This paper describes the neutronic benchmarks and results obtained by various participants of FP7 project EVOL ROSATOM MARS. The aim was two-fold: first to verify validate each code packages partners, adapted for liquid-fueled reactors, second check dependence core characteristics nuclear data set application on a molten salt fast reactor (MSFR). MSFR operates with thorium fuel cycle can be started 233 U-enriched U and/or TRU elements as initial fissile load. All three compositions were...
Abstract Particle therapy (PT) used for cancer treatment can spare healthy tissue and reduce toxicity. However, full exploitation of the dosimetric advantages PT is not yet possible due to range uncertainties, warranting development range-monitoring techniques. This study proposes a novel technique introducing unexplored concept simultaneous detection imaging fast neutrons prompt-gamma rays produced in beam-tissue interactions. A quasi-monolithic organic detector array proposed, its...
A numerical study is performed in order to evaluate the performance and optimal operating conditions of fluidized bed pyrolysis reactors used for condensable tar production from biomass. For this purpose, a previously validated biomass particle model coupled with detailed hydrodynamic binary gas mixture. The kinetics scheme based on superimposed cellulose, hemicellulose, lignin reactions. Any feedstock can be simulated through knowledge its initial mass composition respect these three...
The highly conformal planned dose distribution achievable in intensity modulated proton therapy (IMPT) can severely be compromised by uncertainties patient setup and range. While several robust optimization approaches have been presented to address this issue, appropriate methods accurately estimate the robustness of treatment plans are still lacking. To fill gap we present Polynomial Chaos Expansion (PCE) techniques which easily applicable create a meta-model engine approximating every...
Verification and validation of multi-physics codes dedicated to fast-spectrum molten salt reactors (MSR) is a very challenging task. Existing benchmarks are meant for single-physics codes, while experimental data absent. This concerning, given the importance numerical simulations have in development fast MSR designs. Here, we propose use coupled benchmark specifically designed assess physics-coupling capabilities aforementioned codes. The focuses on specific characteristics MSRs features...
This paper presents the development, validation, and results of a three-dimensional, time-dependent, coupled-neutronics–thermal-hydraulic calculational scheme for channel-type molten salt reactors (MSRs). The reactor physics part is based on diffusion theory, extended by term representing flow fuel through core. calculation temperature field done modeling all channels, which are coupled to each other three-dimensional heat conduction equation. For purpose MSR Experiment (MSRE)...
The DALTON-THERMIX code system has been developed for safety analysis and core optimization of pebble-bed reactors. consists the new three-dimensional diffusion DALTON, which is coupled to existing thermal-hydraulic THERMIX. These codes are linked a database procedure generation neutron cross sections using SCALE-5.The behavior reactors during loss forced cooling (LOFC) transient particular interest since absence could lead significant increase temperature coated particle fuel. Therefore,...
This paper focuses on the freeze-plug, a key safety component of Molten Salt Fast Reactor, one Gen. IV nuclear reactors that must excel in safety, reliability, and sustainability. The freeze-plug is valve made frozen fuel salt, designed to melt when an event requiring core drainage occurs. Melting draining be passive, relying decay heat gravity, occur before reactor incurs structural damage. In this work, we preliminarily investigate melting behavior, assessing influence various design...