Reaktorska fizika (Slovene)

Research programme will cover all important aspects of reactor physics which define the foundations for development of computational and experimental methods for analysis of power and experimental reactors as well as subcritical multiplication systems. Main areas of research will comprise: Nuclear data processing, Methods for fuel cell calculations, Methods for global reactor calculations, Measurements and calculations of fuel burn-up, Monte Carlo modelling and calculations in demanding geometries, And, as a spin-off, Monte Carlo in medicine (BNCT, inverse treatment planning). For nuclear data processing we intend to study newest databases (e. g. ENDF-B/VI) and their applicability for various realistic and test cases. Our target is to check and ammeliorate the quality of available data. Sensitivity analysis will be used. New more precise methods for homogenisation and parametrisation of group constants will be sought in order to improve the methods for fuel cell and global reactor calculations. New methods for fuel burn-up determination based on integral experiments will be studied. Monte Carlo studies of power and research reactors will be continued. MCNP and ENDF-B/VI based crossection libraries will be used. Variance reduction methods (DSA and WW) will be studied in demanding reactor geometries and in adjacent irradiation facilities The main purpose of these studies is to develop a BNCT irradiation facility suitable for clinical use. Monte Carlo methods will be used to further improve precise planning of dose distribution in radiooncology. Inverse treatment planning will be researched intensively. This method seems particularly promising due to its outstanding precision (in spite of the fact that this method is computationally very demanding) and its promise for further automation (irradiation geometry can be defined directly - and automatically - from a CT scan).