You are welcome to submit your application no later than 30 May 2018, UFV-PA 2018/1388.
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The Department of Physics and Astronomy, Division of Applied Nuclear Physics, conducts research in the areas of nuclear reactions (for applications like nuclear energy, cancer therapy or transmutation of nuclear waste), nuclear fuel diagnostics and safeguards (encapsulation of spent nuclear fuel, the future needs of nuclear power plants, nuclear safeguards and non-proliferation issues), neutron diagnostics for fusion energy (studying fusion as a possible future energy source in present day devices and for ITER) and interaction of high velocity ions in various materials (with applications ranging from archaeology and medicine to the ageing of materials in nuclear reactors). The Division of Applied Nuclear Physics offers training and expertise in instrumentation, numerical modelling and computer simulation of nuclear reactions and interactions as well as nuclear measurements techniques.
The fission group focuses on measurement techniques, instrumentation and analysis methods for the (fission) nuclear energy sector, for usage in nuclear fuel diagnostics and safeguards, and in future reactor concepts. We are developing techniques that utilize various radiation types to examine nuclear materials, e.g. neutron transmission tomography, gamma spectroscopy and tomography, and Cherenkov imaging.
Nuclear safeguards are measures undertaken by states to ensure compliance with international treaties and to prevent the use of nuclear materials for non-peaceful applications. The verification of nuclear material using non-destructive assay is an example of such measures. Traditionally, data from various instruments is typically analysed separately. We have however, based on earlier work, reason to believe that it is advantageous to simultaneously analyse multiple signatures using multivariate data analysis (MVA). The application of such analysis techniques to the field of nuclear safeguards is a relatively new approach, and our goal is to assess its potential.
Within this project, we want to investigate possibilities and limitations of applying MVA to data from non-destructive measurements with respect to verifying nuclear material in both existing and future nuclear fuel cycles (Gen IV). The work will include efforts to improve the capability to verify nuclear fuel on the gross and partial defect level especially before fuel encapsulation and storage in so-called difficult-to-access storages, as well as efforts to strengthen nuclear safeguards of future nuclear fuel cycles. With respect to Gen IV systems, such work may include e.g. detailed studies of Gen IV concepts. One example could be the Molten Salt Reactor concept and its different fuel cycle steps, in order to model material flows, detector systems, and modelled measurement data. It is also possible that the work will include experimental measurements of spent nuclear fuel from light water reactors, in order to validate the models.