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Post-irradiation examinations of dispersion fuel rods with modified zirconium alloys claddings
https://doi.org/10.22349/1994-6716-2018-95-3-206-212
Abstract
Modified zirconium alloys E635Mand E635opt based on E635 alloy (E635 was selected as master alloy) have been developed at Bochvar Institute. Fuel rods with such claddings were manufactured at Bochvar Institute and were irradiated at MIR reactor (SC RIAR, Dimitrovgrad). The results from the PIE performed at RIAR are presented. Such features of claddings as microstructures, corrosion resistance (width and structure of oxide), hydrogen contents, distribution of hydrides, mechanical properties were examined and discussed. Modifications of the alloy E635opt and E635M showed higher resistance to corrosion and hydrogen pick-up compared to the E635 alloy, while maintaining high strength and ductility. They have confirmed their prospects for use as cladding for fuel rods with enhanced characteristics.
About the Authors
G. V. Kulakov
A.A. Bochvar High-Technology Scientific ResearchInstitute for Inorganic Materials (VNIINM)
Russian Federation
Russian Federation
Cand Sc. (Eng)
5a, Rogova St, 123098, Moscow
Y. V. Konovalov
A.A. Bochvar High-Technology Scientific ResearchInstitute for Inorganic Materials (VNIINM)
Russian Federation
Russian Federation
Cand Sc. (Eng)
5a, Rogova St, 123098, Moscow
A. A. Kosaurov
A.A. Bochvar High-Technology Scientific ResearchInstitute for Inorganic Materials (VNIINM)
Russian Federation
5a, Rogova St, 123098, Moscow
Russian Federation
5a, Rogova St, 123098, Moscow
M. M. Peregud
A.A. Bochvar High-Technology Scientific ResearchInstitute for Inorganic Materials (VNIINM)
Russian Federation
5a, Rogova St, 123098, Moscow
Russian Federation
5a, Rogova St, 123098, Moscow
V. Y. Shishin
NRC ”Research Institut of Nuclear Reactors»
Russian Federation
Russian Federation
Cand Sc. (Eng)
9, Sapadnoe shosse, 433510, Ulianovskaia obl., Dimitrovgrad
A. A. Sheldyakov
NRC ”Research Institut of Nuclear Reactors»
Russian Federation
9, Sapadnoe shosse, 433510, Ulianovskaia obl., Dimitrovgrad
Russian Federation
9, Sapadnoe shosse, 433510, Ulianovskaia obl., Dimitrovgrad
References
1. Nikulina, A.V., Noduliarnaya korroziya tsirkoniyevykh izdeliy, [Nodular corrosion of zirconium products], Voprosy atomnoy nauki i tekhniki. Series: Materialovedenie i novye materialy, 2012, No 1 (72), pp. 79–89.
2. Nikulina, A.V., Markelov V.A., Peregud M.M., Voevodin V.N., Panchenko V.L., Kobyliansky, G. P., Irradiation-Induced Microstructural Changes inZr-1% Sn-1% Nb-0.4% Fe, Journal of Nuclear Materials, 1996, V. 238, pp. 205–210.
3. Lee, K., Hong, S., Zirconium hydrides and their effect on the circumferential mechanical properties of Zr-Sn-Fe-Nb tubes, Journal of Alloy and Compound, 2002, V. 346 (1–2), pp. 302–307.
4. Min, S., Kim, M., Kim, K., Cooling rate- and hydrogen content–dependent hydride reorientation and mechanical property degradation of Zr–Nb alloy claddings, Journal of Nuclear Materials, 2013, V. 441, pp. 306–314.
5. Kulakov, G.V., Vatulin, A.V., Konovalov, Yu.V., Kosaurov, A.A., Peregud, M.M., Korotchenko, E.A., Shishin V.Yu., Sheldiakov, A.A., Analiz vliyaniya napryazhennodeformirovannogo sostoyaniya obluchennykh obolochek tvelov iz tsirkoniyevykh splavov na oriyentatsiyu gidridov [Analysis of the influence of the stress-strain state of irradiated fuel rod claddings from zirconium alloys on the orientation of hydrides], Atomnaya energiya, 2017, V. 122, No 2, p. 73–77.
6. Kolesnik, M.Yu., Aliev, T.N., Likhansky, V.V., Modelirovanie pereorientatsii gidridov v obolochkakh tvelov, otrabotavshikh TVS v usloviyakhsukhogo khraneniya [Modeling of the reorientation of hydrides in fuel rod claddings of spent fuel assemblies under conditions of dry storage], Voprosy Materialovedeniya, 2016, No 4 (88), pp. 1–13.
7. Shishov, V.N., Evoliutsiya mikrostruktury i deformatsionnaya stabilnost splavov Zr-Nb-(Fe-SnO) pod deistviem oblucheniya [Evolution of microstructure and deformation stability of Zr-Nb-(Fe-Sn-O) alloys under irradiation], Voprosy atomnoy nauki i tekhniki. Seriya: Materialovedenie i novye materialy, 2012, Issue 1 (72), pp. 90–106.
Review
For citations:
Kulakov G.V., Konovalov Y.V., Kosaurov A.A., Peregud M.M., Shishin V.Y., Sheldyakov A.A. Post-irradiation examinations of dispersion fuel rods with modified zirconium alloys claddings. Voprosy Materialovedeniya. 2018;(3(95)):206-212. (In Russ.) https://doi.org/10.22349/1994-6716-2018-95-3-206-212
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