Studying the minor actinides burnup in the fast reactor core
Authors: Zimin V.A., Stolotnyuk Yа.D., Semishin V.V. | |
Published in issue: #6(95)/2024 | |
DOI: | |
Category: Power, Metallurgic and Chemical Engineering | Chapter: Nuclear power plant |
|
Keywords: minor actinides, irradiated nuclear fuel, transmutation, fast reactors, closed nuclear fuel cycle, isotopic composition |
|
Published: 04.01.2025 |
This work objective lies in studying the burnup processes of the minor actinides (MA) positioned in the fast reactor core with the sodium coolant for their transmutation. The paper assesses isotopic and quantitative composition of the irradiated nuclear fuel of a water-moderated thermal power reactor in terms of the minor actinides to determine composition of the transmuted MA mixture, which could be loaded potentially in a fast reactor. The minor actinides homogeneous and heterogeneous loading in the fuel assembly is computationally simulated to study the effect of various arrangements of the MA isotopic mixture in the fast reactor on the transmutation efficiency. Based on the obtained results analysis, the considered methods of the MA arrangement are compared, and their features, advantages and disadvantages are identified.
References
[1] Ganev I.Kh., Lopatkin A.V., Orlov V.V. Homogeneous transmutation of Am, Cm, Np in the core of a BREST-type reactor. Atomic Energy, 2000, Vol. 89, pp. 355–361. (In Russ.).
[2] Ryzhkov S.N., Petrushkov V.A. Study of modern methods of transmutation of minor actinides in thermal and fast reactors. Issues of Atomic Science and Technology. Series: Nuclear Reactor Constants, 2022, iss. 2, pp. 5–31. (In Russ.).
[3] Gulevich A.V., Eliseev V.A., Klinov D.A. et al. Possibility of americium burning in fast reactors. Atomic Energy, 2020, Vol. 128, iss. 2, pp. 82–87. (In Russ.).
[4] Adamov E.O., Dragunov Yu.G., Orlov V.V. et al. Engineering of Nuclear Technology. Vol. IV-25. Moscow, Mashinostroenie Publ., 2005, 960 p. (In Russ.).
[5] Shkarovsky D.A., ed. Description of the application and instructions for users of programs assembled from modules of the MCU-5 package. Moscow, MEPhI Publ., 2012, 146 p. (In Russ.).
[6] Rezepov V.K., Denisov V.P., Kirilyuk N.A. et al. WWER-1000 reactors for nuclear power plants. Podolsk, Gidropress Publ., 2004, 333 p. (In Russ.).
[7] Koning A.J., Rochman D., Sublet J. et al. TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology. Nuclear Data Sheets, 2019, vol. 155, no. 1. (In Russ.). https://doi.org/10.1016/j.nds.2019.01.002
[8] Beltyukov A.I., Karpenko A.I., Poluyaktov A.I. et al. Nuclear power plants with fast neutron reactors with sodium coolant. In 2 parts. Part 1. Ekaterinburg, UrFU Publ., 2013, 548 p. (In Russ.).
[9] Murogov V.M., Vankov A.A., Ilyunin V.G. Prospects for using metallic fuel in fast reactors. Obninsk, IPPE Publ., 1988, 64 p. (In Russ.).
[10] Ganev I.Kh., Lopatkin A.V., Orlov V.V. Heterogeneous transmutation of Am, Cm, Np in the core of the BREST reactor. Atomic Energy, 2000, vol. 89, pp. 362–365. (In Russ.).