Radionuclide neutron source trajectories in the closed nuclear fuel cycle

• Autorzy: Stanisz Przemysław , Cetnar Jerzy , Oettingen Mikołaj

Identyfikatory

DOI

10.2478/nuka-2019-0001

• Języki publikacji: EN

Abstrakty

EN

The highest efficiency in the usage of nuclear energy resources can be implemented in fast breeder reactors of generation IV. It is achieved thanks to the ability of consuming minor actinides (MAs) in energy production. One of the options to use this benefit is full recycling of MAs to close the nuclear fuel cycle. Monte Carlo burn up (MCB), an integrated burn-up calculation code, deals with the complexity of the burn-up process which is applied to the European Lead-cooled Fast Reactor (ELFR). MCB uses continuous energy representation of cross section and spatial effects of full core reactor model; however, it automatically calculates nuclide production in all possible reactions or decay channels. Multi-recycling of MAs can cause an intensified build-up of curium, berkelium and californium. Some of their isotopes are strong neutron emitters from spontaneous fission, which hinders fuel recycling. The implementation of a novel methodology for trajectory period folding allows us to trace the life cycle of crucial MAs from the beginning of the reactor life towards the state of adiabatic equilibrium. The result of the analysis performed is presented, showing the sources of strong contribution to the neutron production rate. The parametric sensitivity analysis method for selected nuclide reactions is applied, revealing sensitivity of transmutation chains for the production of neutron emitter isotopes.

Słowa kluczowe

EN

MCB; transmutation; equilibrium fuel cycle; LFR; trajectory period folding

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2019
• Tom: Vol. 64, No. 1
• Strony: 3--9
• Opis fizyczny: Bibliogr. 15 poz., rys.

Twórcy

autor

Stanisz Przemysław

• Department of Nuclear Energy Faculty of Energy and Fuels AGH University of Science and Technology 30 A. Mickiewicza Ave., 30-059 Krakow, Poland

autor

Cetnar Jerzy

• Department of Nuclear Energy Faculty of Energy and Fuels AGH University of Science and Technology 30 A. Mickiewicza Ave., 30-059 Krakow, Poland

autor

Oettingen Mikołaj

• Department of Nuclear Energy Faculty of Energy and Fuels AGH University of Science and Technology 30 A. Mickiewicza Ave., 30-059 Krakow, Poland

Bibliografia

• 1. Artioli, C., Grasso, G., & Petrovich, C. (2010). A new paradigm for core design aimed at the sustainability of nuclear energy: the solution of the extended equilibrium state. Ann. Nucl. Energy, 37, 915–922. https://doi.org/10.1016/j.anucene.2010.03.016.
• 2. Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modeling of fourth generation nuclear reactors. Comput. Sci., 16(4), 329–350.
• 3. Stanisz, P., Oettingen, M., & Cetnar, J. (2016). Monte Carlo modeling of Lead-Cooled Fast Reactor in adiabatic equilibrium state. Nucl. Eng. Des., 301, 341–352.https://doi.org/10.1016/j.nucengdes.2016.02.025.
• 4. Stanisz, P., Cetnar, J., & Domańska, G. (2015). Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without longlived nuclear waste. Nukleonika, 60(3), 581–590. DOI: 10.1515/nuka-2015-0111.
• 5. Cetnar, J., Stanisz, P., & Domańska, G. (2013). Adiabatic fuel cycle assessment of LFR core with MOX using MCB system. Study for the LEADER project of European Union’s 7th FP EURATOM. Kraków: AGH University, WEiP. (KEJ/2013/4).
• 6. Cetnar, J., Stanisz, P., & Domańska, G. (2013). Transition to the adiabatic-LFR: preliminary definition of the start-up core and MA-burning capabilities evaluation. Report for the LEADER project of European Union’s 7th FP EURATOM. Kraków: AGH University, WeiP. (KEJ/2013/5).
• 7. Cetnar, J. (2006). General solution of Bateman equations for nuclear transmutations. Ann. Nucl. Energy, 33, 640–645. DOI: 10.1016/j.anucene.2006.02.004.
• 8. Cinotti, L., Smith, C. F., Siennicki, J. J., Abderrahim, H. A., Benamati, G., Locatelli, G., Monti, S., Wider, H., Struwe, D., Orden, A., & Hwang, S. (2007). The potential of the LFR and the ELSY project. In International Congress on Advances in Nuclear Power Plants (ICAPP 2007): The nuclear renaissance at work. Proceedings of a meeting held 13–18 May 2007, Nice, France (Vol. 5, pp. 3231–3240). Societe Francaise d’Energie Nucleaire (SFEN).
• 9. Mills, R. W. (2007). Future requirements of nuclear data for the handling, reprocessing and disposal of spent nuclear fuel. In International Conference on Nuclear Data for Science and Technology. DOI: 10.1051/ndata:07730.
• 10. Döderlein, C., Tucek, K., Cetnar, J., Grasso, G., & Stanisz, P. (2012). Definition of the ELFR core and neutronic characterization, Lead-cooled European Advanced Demonstrator Reactor. European Commission Directorate-General JRC. (DEL 005-2011).
• 11. OECD NEA Data Bank. (2006). Processing of the JEFF-3.1 Cross Section Library into Continuous Energy Monte Carlo Radiation Transport and CriticalityData Library. (NEA/NSC/DOC18).
• 12. Firestone, R. B., Shirley, V., Baglin, C., Chu, S., & Zipkin, J. (1996). Table of isotopes 8E. New York: John Wiley & Sons, Inc.
• 13. Mills, R. W. (2008). Nuclear data for the handling, reprocessing and disposal of spent nuclear fuel. UK:Nexia Solutions Ltd., Sellafi eld Works.
• 14. Bays, S., Piet, S., Pope, M., Youinou, G., Dumontier, A., & Hawn, D. (2009). Transmutation dynamics: Impacts of multi-recycling on fuel cycle performances. Idaho National Laboratory. (INL/EXT-09 16857).
• 15. OECD Nuclear Energy Agency. (2015). Review of integral experiments for minor actinide management. (NEA no. 7222).

Uwagi

Opracowanie rekordu w ramach umowy 509/P-DUN/2018 ze środków MNiSW przeznaczonych na działalność upowszechniającą naukę (2019).