Investigation of the corrosion resistance of nickel-based alloys in fluoride melts

Soviet Atomic Energy - 2006
V. V. Ignat’ev1, A. I. Surenkov1, I. P. Gnidoi1, V. I. Fedulov1, V. S. Uglov1, A. V. Panov2, V. V. Sagaradze2, V. G. Subbotin2, A. D. Toropov2, V. K. Afonichkin3, A. L. Bove3
1Russian Science Center Kurchatov Institute, Russia
2Russian Federal Nuclear Center — All-Russia Research Institute of Technical Physics, Russia
3Institute of High-Temperature Electrochemistry, Ural Branch of the Russian Academy of Sciences, Russia

Tóm tắt

The results of tests of the compatibility of nickel-based alloys and metal-fluoride melts are generalized for molten-salt reactors. The structure and strength characteristics of the alloys Kh80MTYu, KhN80M-VI, and MONIKR in the initial state, after thermomechanical treatment and quenching, exposure for 1200 h to thermal convection loop filled with 58NaF-15LiF-27BeF2 with heating by 100°C, are investigated. A method for removing impurities from the melt has been developed. The results of corrosion tests performed on samples of nickel-based alloys in a setup with natural circulation with maximum melt temperature up to 700°C and redox potential of the system 1.25–1.33 V relative to a beryllium comparison electrode are presented. It is shown that deep removal of oxidizing impurities from the melt and maintaining a low redox potential give slow uniform corrosion (less than 5 µm/yr) of Kh80MTYu and KhN80M-VI samples. After the tests were completed, none of the alloys studied exhibited any tendency toward intercrystallite absorption.

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Tài liệu tham khảo

J. Koger, Intergranular Corrosion of Hastelloy N, ORNL-4782 (1972), pp. 123–126.

J. Keiser, Compatibility Studies of Potential Molten Salt Breeder Reactor Materials in Molten Fluoride Salts, ORNL-TM-5783 (1977).

J. Engel, Development Status and Potential Program for Development of Proliferation Resistant MSR, ORNL-TM-6415 (1979), pp. 95–101.

D. Williams, L. Toth, and K. Clarno, Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), ORNL-TM-2006/12 (2006), pp. 45–61.

V. M. Novikov, V. V. Ignat’ev, V. I. Fedulov, and V. N. Cherednikov, Molten Salts in Nuclear Power Systems: Prospects and Problems, Énergoatomizdat, Moscow (1990).

V. Ignatiev, O. Feynberg, V. Subbotin, et al., “Integrated study of molten Na, Li, Be/F salts for LWR waste burning in accelerator driven and critical systems,” in: Proceedings of the GLOBAL International Conference, Tsukuba, Japan (2005), Paper No. 27.

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Soviet Atomic Energy

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