At the CEA Bruyeres les chateles I lecture on using the JSI TRIGA Mark II reactor for FT-TIMS method. This method is a very sensitive methdo for detection of nuclear materias and is used for safeguards purposes
B.04 Guest lecture
COBISS.SI-ID: 28567847In this master’s thesis a new method for conversion of 3D CAD models to a format suitable for Monte Carlo neutron transport is presented. The method is based on scripts written in the Grasshopper add-on for the Rhino graphic design software. The thesis provides a description of the scripts used for writing input for planes, cylinders, cones and boxes. The result of these scripts is a detailed model of the concrete structure of a typical pressurized water nuclear power plant. The model was used in combination with a preexisting model of the core of a typical pressurized water reactor (PWR) to calculate neutron spectra in the pressure vessel and the reactor cavity. The spectra were compared with deterministic calculations. In further tests the model was used used to calculate neutron fluxes and doses in the penetrations of the hot and cold leg of the reactor coolant loop. The model was also applied to determine possible locations of neutron shields in the hot and cold leg penetrations. The results are given in tables and presented graphically. In the conclusion section further applications of the model and scripts for conversion of CAD models to formats suitable for Monte Carlo neutron transportation are discussed.
D.10 Educational activities
COBISS.SI-ID: 2845540Independent evaluation of the NPP Krško cycle 28 reload safety evaluation
F.30 Professional assessment of the situation
COBISS.SI-ID: 29304359explaining fusion as possible energy source of the future
D.11 Other
COBISS.SI-ID: 11007828This thesis gives an overview of TRIGA mk.II irradiation facilities and possibilities, concentrating on silicon sample irradiation. The goal was to investigate possibilities of irradiation in the TRIGA fission reactor, with neutron dose being as low as possible. First, a neutron filter is considered in the Thermalising collumn of the TRIGA reactor, in form of a slab in neutron tunnel channel. The slab acts also as a source, where -rays are promptly generated by neutron absorption. Secondly, activation of isotopes trough neutron activation and nuclear fission, making them radioactive, and producing radiation, for fuel elements and other materials was considered. Activation calculations for fuel elements in their respective positions and for various other materials in neutron irradiation chambers inside TRIGA reactor were done and analyzed. For the purposes of the analysis, Monte Carlo particle transport methods and neutron activation and transmutation calculations methods were used. Additionally, a script for analysis of irradiation with delayed rays, coupling time-independent Monte Carlo particle transport calculations and time-dependent neutron activation and transmutation calculations via R2S method, was developed.
D.10 Educational activities
COBISS.SI-ID: 2858084