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Determining the Characteristics of the Tritium Diffusion in the Structural Material of the Liquid-Salt Reactor

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The paper sets out the results of a study into the characteristics of tritium diffusion in the structural material of a liquid-salt reactor as represented by KhN80MTYu alloy. The studies were carried out using membrane and radioluminographic methods in the temperature range of 450–750°C. NP2 grade nickel was used as a reference material. KhN80MTYu alloy was established to have the significantly lower characteristics of the tritium diffusion as opposed to the pure nickel of the NP2 grade with no kinks in temperature dependencies. An exposure in the melt of ammonium bifluoride was established to increase the diffusion coefficient of tritium. This may mean that the action of the fuel salt melt on the wall during the reactor operation may accelerate the tritium diffusion.

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References

  1. M. Anderson, K. Sridharan, D. Morgan, et al., Heat Transfer Salts for Nuclear Reactor Systems-Chemistry Control, Corrosion Mitigation, and Modeling, Univ. of Wisconsin, Univ. of California, PNNL (2015).

  2. H. Schmutz, P. Sabharwall, and C. Stoots, Tritium Formation and Mitigation in High Temperature Reactors, US (2012).

  3. Y. Qiao, F. Liu, C. Zhang et al., “The sources and control of tritium in molten salt reactor,” Adv. Mater. Res., 953, 609–613 (2014).

    Article  Google Scholar 

  4. N. A. Galaktionova, Hydrogen in Metals, Metallurgiya, Moscow (1967).

    Google Scholar 

  5. K. Katayama, T. Matsumoto, A. Ipponsugi, et al., “Tritium permeation from tritiated water to water through Inconel,” Nucl. Mater., 565, 153–723 (2022).

    Article  Google Scholar 

  6. J. Kärger and P. Heitjans, Diffusion in Condensed Matter: Methods, Materials, Models, Springer, NY (2005), pp. 417–460.

  7. R. Lässer, Properties of Protium, Deuterium and Tritium in Selected Metals. Tritium and Helium-3 in Metals, Springer, Berlin (1989).

  8. OST 95 10447-91, Structural Materials for Nuclear Reactors. Method of Research Reactor Tests for Hydrogen Permeability, Moscow (1992).

  9. A. A. Semenov, A. S. Anikin, A. V. Lizunov, et al., “Approximation of the hydrogen leakage process during its diffusion through metal membranes,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Novye Mater., No. 4(110), 23–35 (2021).

  10. N. P. Bobyr’, I. G. Lesina, A. A. Semenov, et al., “Study of the tritium distribution in structural and functional materials using the radioluminographic method,” Analitika, 11, No. 1, 40–45 (2021).

  11. I. G. Lesina, A. A. Semenov, A. S. Anikin, et al., “Radioluminography as a highly informative method of studying tritium-containing materials,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Novye Mater., No. 4, 81–90 (2019).

  12. B. V. Ivanov, A. S. Anikin, A. N. Bukin, et al., “Measurement of the hydrogen diffusion coefficient in zirconium alloys using the method of radioluminography,” Fiz. Khim. Obrab. Mater., No. 2, 81–91 (2018).

  13. V. V. Ignat’ev, Conctruction of Experimental Plants and a Database for the Selection and Improvement of Liquid-Salt Fuel Compositions and Coolants of Nuclear Reactors: Diss. Cand. Sci. (Engineering), NRC Kurchatov Institute, Moscow (2007).

  14. GOST 492-2006, Nickel, Nickel, and Copper-Nickel Alloys Formed by Pressure. Grades, Moscow (2011).

  15. M. Wang, Y. Zhou, X. Tan, et al., “Nickel hollow fiber membranes for hydrogen separation from reformate gases and water gas shift reactions operated at high temperatures,” Membrane Sci., 575, 89–97 (2019).

    Article  Google Scholar 

  16. I. S.Grigor’ev and E. Z. Meilikhov (eds.), Physical Quantities: Reference Book, Energoatomizdat, Moscow (1991).

  17. D. Grant, D. Cummings, and D. Blackburn, “Hydrogen in 304 steel – diffusion, permeation and surface reaction,” Nucl. Mater., 149, 180–191 (1987).

    Article  ADS  Google Scholar 

  18. D. Grant, D. Cummings, and D. Blackburn, “Hydrogen in 316 steel – diffusion, permeation and surface reaction,” Nucl. Mater., 152, 139–145 (1988).

    Article  ADS  Google Scholar 

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Correspondence to A. S. Anikin.

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Translated from Atomnaya Énergiya, Vol. 133, No. 5–6, pp. 265–271, November–December, 2022.

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Anikin, A.S., Semenov, A.A., Lizunov, A.V. et al. Determining the Characteristics of the Tritium Diffusion in the Structural Material of the Liquid-Salt Reactor. At Energy 133, 279–287 (2023). https://doi.org/10.1007/s10512-023-01009-z

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  • DOI: https://doi.org/10.1007/s10512-023-01009-z

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