Abstract
The results of calculations of the neutron-physical characteristics of three variants of the fuel load in a VVÉR-1000 core are presented: a load consisting completely of enriched natural uranium (standard fuel) or reprocessed uranium-plutonium fuel from the first and second recycles. The calculations were performed for a stationary load of the core with a four-year fuel run. The difference between the neutron-physical characteristics of a core with a full load of uranium and reprocessed uranium-plutonium fuel is discussed. An analysis of the neutron-physical characteristics did not show any fundamental limitations for a possible 100% load of reprocessed uranium-plutonium fuel in a VVÉR-1000 core.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
A. Yu. Gagarinskii, V. V. Ignat’ev, N. N. Ponomarev-Stepnoi, et al., “Role of nuclear power in the structure of world energy production in the 21st century,” At. Énerg., 99, No. 5, 323–336 (2005).
B. V. Nikipelov and V. B. Nikipelov, “Fate of reprocessed uranium,” Byul. At. Énerg., No. 9, 35–43 (2002).
V. N. Proselkov, S. S. Aleshin, S. G. Popov, et al., “Analysis of the possibility of using reprocessed uranium based fuel in VVÉR,” At. Énerg., 95, No. 6, 422–428 (2003).
V. V. Gorskii, “State and prospects for using MOX fuel in light-water reactors,” At. Énerg. Rubezh., No. 6, 8–15 (2000).
B. Tinturier, M. Debes, and J. Delbecq, “Perspective on the french flosed fuel cycle: open towards energy future and sustainability,” in: Proceedings of the International Conference Global’2005, Tsukuba, Japan, October 9–13, 2005, Paper IL005, p. 6.
Yu. S. Fedorov, B. A. Bibichev, B. Ya. Zil’berman, and E. G. Kudryavtsev, “Use of reprocessed uranium and plutonium in thermal reactors,” At. Énerg., 99, No. 2, 136–141 (2005).
Yu. S. Fedorov, E. G. Kudryavtsev, B. A. Bibichev, et al., “Use of regenerated uranium and plutonium in WWER reactors,” in: Proceedings of the International Conference Global’2005, Tsukuba, Japan, Oct. 9–13, 2005, Paper 124, p. 5.
A. N. Novikov, “Development of VVER physical calculation codes,” in: Proceedings of the 10th Symposium of AER, Moscow, Russia, Oct. 18–22, 2000, Vol. 1, pp. 433–448.
Author information
Authors and Affiliations
Additional information
__________
Translated from Atomnaya Énergiya, Vol. 101, No. 6, pp. 407–413, December, 2006.
Rights and permissions
About this article
Cite this article
Pavlovichev, A.M., Pavlov, V.I., Semchenkov, Y.M. et al. Neutron-physical characteristics of a VVÉR core with 100% load of reprocessed uranium and plutonium fuel. At Energy 101, 863–868 (2006). https://doi.org/10.1007/s10512-006-0182-5
Received:
Issue Date:
DOI: https://doi.org/10.1007/s10512-006-0182-5