33 research outputs found
Gamma en neutronafscherming: Deskundigheidsniveau 2
Dictaat in opdracht van het Interuniversitair onderzoekinstituut voor Radiopathologie en Stralenbescherming (IRS) te Leiden en het Interfacultair Reactor Instituut (IRI) te Delft.Applied Science
Topic 3. Decay Heat Predictions: Experiments, Methods and Data. Integral validation and decay heat standards.
Applied Science
Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor
The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained in the study of the closed fuel cycle and the influence of the addition of extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In the presented work, up to 10% of the fuel was homogeneously replaced by an MA-mixture. The results are that addition of MA increases the potential of obtaining a closed fuel cycle. Reactivity coefficients generally decrease with increasing MA content. Addition of MA reduces the reactivity swing and allows very long irradiation intervals up to 10% FIMA with a small reactivity swing. Multirecycling studies show that a 600?MWth GCFR can transmute the MA from several PWRs. By a careful choice of the MA-fraction in the fuel, the reactivity of the fuel can be tuned to obtain a preset multiplication factor at end of cycle. Preliminary decay heat calculations show that the presence of MA in the fuel significantly increases the decay heat for time periods relevant to accidents (104β105 s after shutdown). The paper ends with some recommendations for future research in this promising area of the nuclear fuel cycle.Radiation, Radionuclides & ReactorsApplied Science
A multi-physics solver for liquid-fueled fast systems based on the discontinuous Galerkin FEM discretization
Performing accurate numerical simulations of molten salt reactors is challenging, especially in case of fast-spectrum designs, due to the unique physics phenomena characterizing these systems. The limitations of codes traditionally used in the nuclear community often require the development of novel high-fidelity multi-physics tools to advance the design of these innovative reactors. In this work, we present the most recent code developed at Delft University of Technology for multi-physics simulations of liquid-fueled fast reactors. The coupling is realized between an incompressible RANS model and an SN neutron transport solver. The models are implemented in two in-house codes, based on the discontinuous Galerkin Finite Element discretization, which guarantees high-quality of the solution. We report and discuss the results of preliminary simulations of the Molten Salt Fast Reactor at steady-state and during a Total Loss of Power transient. Results prove our code has capabilities for steady-state and transient analysis of non-moderated liquid-fueled reactors.RST/Reactor Physics and Nuclear MaterialsRST/Radiation, Science and Technolog