On the neutronics of European lead-cooled fast reactor

• Autorzy: Cetnar J. , Oettingen M. , Domańska G.
• Języki publikacji: EN

Abstrakty

EN

The perspective of nuclear energy development in the near future imposes a new challenge on a number of sciences over the world. For years, the European Commission (EC) has sponsored scientific activities through the framework programmes (FP). The lead-cooled fast reactor (LFR) development in the European Union (EU) has been carried out within European lead-cooled system (ELSY) project of the 6th FP of EURATOM. This paper concerns the reactor core neutronic and burn-up design studies. We discuss two different core configurations of ELSY reactor; one loaded with the reference – mixed oxide fuel (MOX), whereas the second one with an advanced fuel – uranium- -plutonium nitride. Both fuels consist of reactor grade plutonium, depleted uranium and additionally, a fraction of minor actinides (MA). The fuel burn-up and the time evolution of the reactor characteristics has been assessed using a Monte Carlo burn-up code (MCB). One of the important findings concerns the importance of power profile evolution with burn-up as a limiting factor of the refuelling interval.

Słowa kluczowe

EN

fuel burn-up; plutonium; minor actinides; oxide fuel; nitride fuel; LFR; ELSY; MCB

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2010
• Tom: Vol. 55, No. 3
• Strony: 317--322
• Opis fizyczny: Bibliogr. 11 poz., rys.

Twórcy

autor

Cetnar J.

autor

Oettingen M.

autor

Domańska G.

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

Bibliografia

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• 2. Cetnar J (2006) Development and applications of MCB – Monte Carlo continuous energy burn-up code. AGH University of Science of Technology, Krakow
• 3. Cetnar J (2006) General solution of Bateman equations for nuclear transmutations. Ann Nucl Energy 33:640–645
• 4. ELSY Work Program, European lead cooled system (ELSY) (2006) Project, FP-036439, 6th Framework Program, EURATOM, Management of radioactive waste
• 5. GEN-IV (2002) A technology roadmap for generation IV nuclear energy systems. US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, GIF-002-00
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• 8. Sobolev V, Malambu E, Aid Abderrahim H (2007) Preeliminary fuel pin, hexagonal assembly and core design for ELSY-600, Derivelable 5, FP6 ELSY, contract no. FI6W-2006-036439
• 9. Thetford R, Mignanelli M (2003) The chemistry and physic of modeling nitride fuels for transmutation. J Nucl Mater 320:44–53
• 10. Tuček K (2004) Neutronic and burnup studies of accelerator-driven system dedicated to nuclear waste transmutation. Doctoral thesis, Royal Institute of Technology, Department of Physics, Stockholm
• 11. Tuček K, Carlsson J, Wider H (2005) Comparison of sodium and lead-cooled fast reactors regarding severe safety and economical issues. In: Proc of the 13th Int Conf on Nuclear Engineering, 16–20 May 2005, Beijing, China, ICONE13-50397