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Nuclear waste, especially the long living fission products as well as the minor actinides requires special handling. A promising way to reduce the amount of long-living waste is to convert it into short-living waste. This can be achieved efficiently in fast critical and subcritical reactors. Since a long time, our institute contributes to respective projects of the EU Framework Programs (FP5, FP6, FP7, H2020) and to industrial partner funded projects. In our institute, we concentrate on the safety evaluation of these inovative reactor concepts that in the future are to be used for nuclear waste transmution.

SUBCHANFLOW code is used to model a fuel element with intact geometry. For transients, belonging to design basis conditions (DBC) or design extention conditions (DEC), fast running in-house codes like SIM-family codes are used. For severe accidents, the system code SAS-SFR, further developed and maintained in our institute, and system code ASTEC-Na are applied.



  1. S. Perez-Martin, A. Ponomarev, R. Kruessmann, D. Struwe, M. Schikorr, W. Pfrang, W. Hering, D. Lemasson, S. Massara, D. Verwaerde, Safety analysis of a sodium-cooled fast reactor with transmutation capabilities. European Nuclear Conf. (ENC 2012), Manchester, GB, December 9-12, 2012 Transactions Advanced Reactors Bruxelles: European Nuclear Society 2012.
  2. A. Alemberti, L. Mansani, M. Frogheri, E. Bubelis, M. Schikorr. The European Lead Fast Reactor: design, safety approach and safety characteristics // Proceedings of the IAEA Technical meeting on Impact of the Fukushima event on current and future fast reactor designs, 19-23 March, 2012. – Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany.
  3. D. De Bruyn, R. Fernandez, L. Mansani, A. Woaye-Hune, M. Sarroto, E. Bubelis. The Fast-spectrum Transmutation Experimental Facility FASTEF: Main Design Achievements (Part 1: Core & Primary System) Within The FP7-CDT Collaborative Project Of The European Commission // Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants – ICAPP 2012, 24-28 June, 2012. – Chicago, USA. 2012. P. 1-9.
  4. E. Bubelis, M. Schikorr, L. Mansani, G. Bandini, K. Mikityuk, Y. Zhang, G. Geffraye. Safety analysis results of the DBC transients performed for the ALFRED reactor // Proceedings of the IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), 4-7 March, 2013. – Paris, France, 2013. P. 1-10.
  5. G. Bandini, E. Bubelis, M. Schikorr, M.H. Stempnievicz, A. Lázaro, K. Tucek, P. Kudinov, K. Kööp, M. Jeltsov, L. Mansani. Safety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor // Proceedings of the IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), 4-7 March, 2013. – Paris, France, 2013. P. 1-10.
  6. A. Lazaro, L. Ammirabile G. Bandini, G. Darmet S. Massara, Ph. Dufour, A. Tosello, E. Gallego, G. Jimenez , K. Mikityuk, M. Schikorr, E. Bubelis, A. Ponomarev, R. Kruessmann, M. Stempniewicz , Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking // Nuclear Engineering and Design. ISSN 0029-5493 / 2014. Vol. 266. – P. 1-16. Part II: Optimised core and representative transients analysis // Nuclear Engineering and Design. ISSN 0029-5493 / 2014. Vol. 277. – P. 265-276.
  7. S. Perez-Martin, W. Pfrang, M. Haselbauer. Analysis of the CABRI-1 Single Fuel Pin LOF Experiment BI1 with SAS-SFR Code including Two-phase Sodium Behaviour // Proceedings of ICAPP 2014, Paper 14048, Charlotte, USA, April 6-9, 2014.
  8. S. Perez-Martin, M. Haselbauer, W. Pfrang, W. Hering. Contribution of KIT to the development of ASTEC-Na code Part II: Two-phase sodium behaviour in the CABRI-1 LOF experiment BI1 // 45th Annual Meeting on Nuclear Technology, Frankfurt, Germany, 6-8 May 2014.
  9. A. Flores y Flores, V. Matuzas, S. Perez-Martin, G. Bandini, S. Ederli, L. Ammirabile, W. Pfrang. Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment // Annals of Nuclear Energy 94, P. 175–188, 2016.