The main domestic and foreign results obtained in the course of reactor tests and post-reactor studies of alloyed fuel are reviewed. The regularities of its radiation swelling and mechanical and chemical interaction with fuel-element cladding are determined. The knowledge accumulated about the properties and behavior under irradiation of alloyed metal fuel can be helpful in designing a fuel element that is serviceable to burnup ≥20% h.a.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
V. M. Murogov, A. A. Vankov, and V. G. Ilyunin, Prospects for Using Metal Fuel in Fast Reactors, Preprint FEI-1913 (1988).
G. Hofman, “Irradiation behavior of experimental Mark-II EBRII driver fuel,” Nucl. Technol., 47, 7–22 (1980).
L. Leibowitz, E. Veleckis, R. Blomquist, and A. Pelton, “Solidus and liquidus temperatures in the uranium–plutonium–zirconium system,” J. Nucl. Mater., 154, No. 1, 145–153 (1988).
D. Harbur, J. Anderson, and W. Maraman, Studies on the U–Pu–Zr Alloy System for Fast Breeder Reactor Applications, LA-4512 (1970).
D. Crawford, D. Porter, and S. Hayes, “Fuels for sodium cooled fast reactors: US perspective,” J. Nucl. Mater., 371, 202–231 (2007).
G. Pahl, D. Porter, C. Lahm, and G. Hofman, “Experimental studies of U–Pu–Zr fast reactor fuel pins in the experimental breeder reactor-II,” Met. Mater. Trans. A, 21, 1863–1870 (1990).
H. Tsai, Yu. Liu, D. Wang, and J. Kramer, “Behaviour of low burnup metallic fuels for the integral fast reactor at elevated temperatures,” in: Int. Conf. on Fast Reactors and Related Fuel Cycles, (1991), pp. 17–28.
A. Cohen, H. Tsai, and T. Neimark, “Fuel/cladding compatibility in high-burnup U–19Pu–10Zr/HT9–clad fuel at elevated temperatures,” in: Int. Symp. on Reliable Fuels for Liquid Metal Reactors, Chicago (1992), pp. 1–19.
A. Cohen, H. Tsai, and L. Neimark, “Fuel/cladding compatibility in U–19Pu–l0Zr/HT9–clad fuel at elevated temperatures,” J. Nucl. Mater., 204, 244–251 (1993).
H. Dohee,Y. Kim, C. Lee, et al., “Conceptual design of the sodium-cooled fast reactor KALIMER-600,” Nucl. Eng. Technol., 39, No. 3, 193–204 (2007).
A. Bochvar, S. Konobeevsky, V. Kutaitsev, et al., “Interaction between plutonium and other metals in connection with their arrangement in mendeleev’s periodic table,” in: U.N. Int. Conf. Peaceful Uses At. Energy 2nd, Geneva (1958), Vol. 6, pp. 184–193.
I. V. Vaganov, G. I. Gadzhiev, N. S. Kosulin, and V. N. Syuzyov, “Development and study of metal alloy fuel based on the alloys U–Zr, U–Pu–Zr for fast reactors,” in: 5th Conf. on Reactor Materials Engineering, NIIAR, Dimitrovgrad (1998), Vol. 1, Pt. 2, pp. 20–28.
I. V. Vaganov, G. I. Gadzhiev, N. S. Kosulin, and V. N. Syuzyov, “Results of tests and post-radiation studies of UPTS-1 fuel assemblies with U–Pu–Zr metal fuel,” in: 6th Conf. on Reactor Materials Engineering, NIIAR, Dimitrovgrad (2000), Vol. 2, Pt. 2, pp. 232–243.
G. I. Gadzhiev and V. N. Syuzyov, “Results of tests of U–Zr and U–Pu–Zr metal alloy fuel in the BOR-60 reactor,” in: 9th Russ. Conf. on Reactor Materials Engineering, NIIAR, Dimitrovgrad (2009), pp. 335–344.
Yu. N. Sokurskii, Ya. M. Sterlin, and V. A. Fedorchenko, Uranium and Its Alloys, Moscow (1971).
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya, Vol. 113, No. 4, pp. 222–228, October, 2012.
Rights and permissions
About this article
Cite this article
Kryukov, F.N., Syuzyov, V.N., Nikitin, O.N. et al. State of metal alloy fuel after irradiation in a fast reactor. At Energy 113, 276–282 (2013). https://doi.org/10.1007/s10512-013-9630-1
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-013-9630-1