81 citations of the journal in the Russian Science Citation Index | Vol. 4 No 1 was published on March 17, 2020. | Clarivate Analytics | Control Committee in Education and Science of the Republic of Kazakhstan |


Investigation of 244Cm dynamics production in a WWER-1200 reactor for fuel based on 235U and MOX fuel

Number 1_Vol.4

AUTHORS: A.M. Petrovski, K.I. Usheva, T.N. Korbut, E.A. Rudak, M.O. Kravchenko, L.F. Babichev

DOI: 10.29317/ejpfm.2020040101

PAGES: 06 - 12

DATE: 2020-03-17


ABSTRACT

244Cm is a very important nuclide due to the high specific heat release and it may become reasonable to recycle the spent nuclear fuel to extract this isotope. In this work, the dynamics of 244Cm isotope production for the fuel assembly of the WWER-1200 reactor with an enrichment of 4.95% and burnup up to 70 MW · day/kg was calculated using Serpent Monte Carlo code. A similar calculations was performed for MOX-based fuel assembly with the same irradiation characteristics. It has been shown that production of 244Cm in high burnup uranium dioxide fuel, and especially in MOX fuel, reaches a high value, which can cause problems during spent fuel management. The main problems associated with the curium relates to the residual heat and neutron activity.


KEYWORDS

 curium-244, spent fuel, WWER-type ractors, high burnup, residual heat.


CITED REFERENCES

[1] M. StaceyWeston, Nuclear Reactor Physics (Second edition) (Wiley-VCH, 2007) 735 p.

[2] J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis (WILEY, 1976) 650 p.

[3] JEFF-3.3 Radioactive Decay Data. https://www.oecd-nea.org/dbdata/jeff/jeff33/index.html#_downloads.

[4] J. Leppaenen, Serpent - a continuous-energy Monte Carlo reactor physics burnup calculation code VTT technical research centre of Finland (2013) 164 p.

[5] Y. Semchenkov, International Nuclear Forum Bulgarian Nuclear Energy "National, Regional andWorld Energy Security", Varna (2010).

[6] Yu. Dragunov, 5th International Scientific and Technical Conference "Ensuring Safety of NPPs with WWER", Podolsk, (2007) http://www.gidropress.podolsk.ru/files/proceedings/mntk2007/disc/autorun/article140-en.htm.

[7] ENDF/B-VII.0: Nucl. Data Sheets 107 (2006) 2931.

[8] T. Korbut, Nuclear Physics and Engineering 8(2) (2017) 118-122.

[9] V. Kolobashkin, Radiation characteristics of irradiated nuclear fuel (M: Energoatomizdat, 1983) 384 p.

[10] O. Samoilov, Proceedings of the 5th International Scientific and Technical Conference "Ensuring the safety of NPP with WWER", Podolsk (2007) 

http://www.gidropress.podolsk.ru/files/proceedings/mntk2007/disc/autorun/article123-en.htm.

[11] V. Molchanov, 6th International Conference on WWER Fuel Performance, Modeling and Experimental Support., Albena (2005).

[12] A. Piatrouski et al., J. Phys.: Conf. Ser. 1133 (2018) 012009.

[13] C.O. Maidana, Nuclear Technologies for Space Exploration: An overview on nuclear thermal and electric propulsion, radioisotope power generators and fission surface power (Review of the Italian Mars Society, 2014).

[14] A. Postulatov, 5th European Conference on Thermoelectrics, Odessa (2007) 

http://ect2007.its.org/ect2007.its.org/proc-contents.html.

[15] N. Bibler, The Journal of Physical Chemistry 78(3) (1974) 211-215.

[16] J. Posey, Process for the recovery of Curium-244 from nuclear waste (ORN L-5687, 1980) 104 p.

[17] EXFOR: International Collaboration Between Nuclear Reaction Data Centres (NRDC), Nucl. Data Sheets 120 (2014) 272.

[18] M. Hiroyuki, Data Book for Calculating Neutron Yields from Reaction (alpha, n) and Spontaneous Fission, Japan Atomic Energy Research Inst. (1992) 268 p. (In Japanese)


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