Nuclear Education and Research at TU Delft
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1 Nuclear Education and Research at TU Delft Jan Leen Kloosterman TU-Delft Delft University of Technology Challenge the future Reactor Institute Delft Research on Energy and Health with Radiation 2 1
2 Some numbers (2015): Faculties 8 Bachelor studies 14 Master studies 30 New students 4500 ( 1500 int l) Total number of students 21,000 (16% int l) Total number Nuclear PhD Energy students & Radiation 2300 Applications ( 1500 int l) Academic staff Student numbers at TU Delft 4 2
3 Nuclear Science and TU-Delft Open for students from Applied Physics, Chemical Engineering and Sustainable Energy Technology (all MSc) Energy Security Health 5 GENERAL Modules Introduction Nuclear Science Eng. (6 EC) Nuclear Chemistry (6 EC) Practical Radiochemistry (3 EC) Neutrons, X-Rays and Positrons for Microscopic Structures and Dynamics (6 EC) Radiological Health Physics (6 EC) Elementary Particle Physics 6 3
4 Nuclear ENERGY Modules Nuclear Reactor Physics (6 EC) Computational Neutron Transport (3 EC) Nuclear Reactor Thermal Hydraulics (3 EC) Chemistry of the Nuclear Fuel Cycle (3 EC) Chemistry and Physics of Actinides (3 EC) Practical (DELPHI, simulator, HOR) 7 Nuclear HEALTH Modules Radiation Detection and Medical Imaging (6 EC) Particle Therapy Holland PTC (6 EC) Particle Radiotherapy (3 EC) Clinical Physics of Medical Imaging (6 EC) Radiotherapy (6 EC) Medical Imaging Signals and Systems (6 EC) 8 4
5 9 Research RID Energy Health 10 5
6 11 OYSTER Project OYSTER for scientific instrumentation Up to 100 times Smaller and 100 times Bigger 12 6
7 Chemistry and Materials Reactors and Applications for Energy Theoretical and and Health Thermal Computational Hydraulics Reactor Physics and Heat Transfer 13 Reactor Physics in Delft 14 7
8 Super-Critical SMR Martin Rohde 15 SCWR Operational Range at 25 MPa SCWR BWR Properties change significantly! 16 8
9 SCWR Stability DELIGHT facility Flow driven by density difference Detailed instrumentation: thermocouples, pressure sensors Artificial neutronic feedback 10 m 17 Annular Flow Laser (LDA) Seeding chamber Optical access unit Release valve Vacuum pump Seeding injection system 18 9
10 Numerical: fixed T at wall, no buoyancy Cartesius cluster, 256 cores Re=10 4 Pr 1 SC CO 2 (80 bars) Very thin boundary layer! 19 Molten Salt Nuclear Reactors Jan Leen Kloosterman 20 10
11 SAMOFAR partners 21 SAMOFAR partners Number Organisation Country 1 (Coord) Technische Universiteit Delft (TU Delft) The Netherlands 2 Centre National de la Recherche Scientifique (CNRS) France 3 JRC - Joint Research Centre- European Commission (JRC) Germany 4 Consorzio Interuniversitario Nazionale per la Ricerca Tecnologica Nucleare (CIRTEN) Italy 5 Institut de Radioprotection et de Sûreté Nucléaire (IRSN) France 6 Centro de Investigaciony de Estudios Avanzados del Instituto Politecnico Nacional (CINVESTAV) Mexico 7 AREVA NP SAS (AREVA) France 8 Commissariat a l Energie Atomique et aux Energies Alternatives (CEA) France 9 Electricité de France S.A. (EDF) France 10 Paul Scherrer Institute (PSI) Switzerland 11 Karlsruher Institut für Technologie (KIT) Germany
12 Aim of the project The grand objective of SAMOFAR is to: prove the innovative safety concepts of the MSFR, deliver breakthrough in nuclear safety and waste management create a consortium of stakeholders to demonstrate the MSFR beyond SAMOFAR Main results are: experimental proof of concept (integral) safety assessment of the MSFR update of the conceptual design of the MSFR roadmap and momentum among stakeholders 23 2 Molten Salt Fast Reactor Working parameters MSFR High temperature (750 0 C) Low pressure (1 bar) Circulation time (4 sec) LiF-ThF4-UF4-(TRU)F3 ( mol%). Online processing / fueling Three (fuel) salt loops 24 12
13 Unique features MS(F)R Fuel salt is at ambient pressure No driving force leading to dispersion Fuel salt is a fluid No compaction of the fuel possible Expansion gives strong negative feedback Freeze plugs to drain the salt Fuel salt cleaning Continuous removal of fission products and uranium Remaining products strongly bound to the salt Flexible fuel cycle Breeding with thorium or uranium Waste burning (Pu/MA from LWR spent fuel) No external fuel processing steps 25 MSR research themes at TU Delft Materials Chemistry fuel cycle, Salt control Reactor physics, Safety analysis, Salt properties Extraction processes Safety analysis 26 13
14 Why is MSR analysis challenging? Materials Geometry Solver neutron transport eqs. Temperature distribution Fluid flow Fuel depletion n x, y, z, E,,, t P x, y, z, t Danny Lathouwers 27 Coupled CFD-Neutronics CFD and neutronics code based on DG RANS turbulence models (k-, k- ) included Energy state and equations of state added 28 2D Taylor vortex benchmarking 2 14
15 Adaptive refinement 29 Uncertainty analysis Materials Geometry Solver neutron transport eqs. Temperature distribution Fluid flow Fuel depletion t nxyze,,,,,, Pxyzt,,, 30 15
16 Uncertainty analysis Materials Geometry Solver neutron transport eqs. Temperature distribution Fluid flow Fuel depletion t nxyze,,,,,, Pxyzt,,, 31 Polynomial chaos expansion: FANISP Zoltan Perko 32 16
17 Holland PTC Deterministic modelling for dose calculation and sensitivity analysis for increased robustness of treatment plans Cooperation with Erasmus MC, LUMC, VARIAN, 33 Uncertainties in proton therapy 34 17
18 Patient Primary tumour is indicated in red (CTV high), high risk areas for metastasis are delineated in yellow (CTV low). The tumour is surrounded by critical organs, such as spinal cord, the brain stem and the salivary glands. 35 Dose volume histogram 36 18
19 DVH plus uncertainties 37 Mo-99 supply chain OPAL ANSTO(Australia) ANSTO(Australia)
20 Mo-99 production steps 1 Target fabrication 2 Target irradiation 3 Target delivery 4 Target cutting 5 Target dissolving 6 Solution treatment 7 Mo-99 recovery 11 Waste collection 8 Mo-99 purification 12 U-235 recovery 9 Mo-99 generator 13 Waste processing 10 Mo-99 pharmacy 14 Waste storage 39 Aqueous Homogeneous Reactor AHR power of 15 kw for 2% Mo-99 demand 40 20
21 OYSTER OYSTER Optimized Reactor Core Installation of Cold Neutron Source Installation of New Instruments and Facilities 41 Isotope production loop 42 21
22 Isotope production loop 2% global demand Mo Geological disposal Basic and chemical research Ceramic Waste forms (e.g. phospates) Migration experiments (U/FP in Clay) Interfaces (concrete/clay) 44 22
23 Nuclear Materials Chemistry Rudy Konings and Anna Smith 45 Thank you for your attention 46 23
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