Abstract
We investigate the influence of alloying with rare-earth elements and metals of groups IV–VI on the hydrogen permeability, diffusion coefficient, and hydrogen solubility in ÉP-838 and Kh12G20V steels proposed as materials for the first wall of a thermonuclear reactor operating on deuterium–tritium plasma. Based on the requirements of ecological safety (hydrogen permeability must be less than 2.4 · 10−8 mole/(m · sec · Pa1/2)), we show that the necessary level of hydrogen permeability of ÉP-838 steel can be reached in the case of alloying with cerium after an additional thermal treatment in hydrogen which initiates the formation of intermetallidic phases of the Fe3Mn type. The value of the hydrogen permeability of Kh12G20V steel corresponds to the level of ecological safety. In this case, alloying with scandium, tungsten, and carbon not only decreases the value of the flow of a diffusing gas fivefold but improves the strength properties due to an increase in the volume fraction of carbide phases.
Similar content being viewed by others
REFERENCES
V. I. Pokhmurs'kyi and V. V. Fedorov, Influence of Hydrogen on Diffusive Processes in Metals [in Ukrainian], Karpenko Physicomechanical Institute, Ukrainian Academy of Sciences, L'viv (1998).
V. I. Pokhmurskii, V. V. Fedorov, P. N. Antonevich, et al., “Change in the phase-structural state of ÉP-838 and 316 SS steels upon interaction with hydrogen,” Fiz.-Khim. Mekh. Mater., 23, No. 6, 42–47 (1987).
V. A. Varoni and E. H. Van Deventer, “Materials consideration in tritium handling systems,” J. Nucl. Mater., No. 85–86, 257–269 (1979).
A. S. Nikiforov, Z. V. Ershova, N. K. Vinogradova, et al., “Numerical estimates of leakage of tritium from the lithium zone of a blanket of an experimental thermonuclear reactor (variant K),” in: Structural Materials for Reactors of Thermonuclear Fusion [in Russian], Nauka, Moscow (1988), pp. 28–33.
V. V. Fedorov, V. I. Pokhmurskii, E. V. Demina, et al., “Change in the hydrogen permeability of 12Kh18N10T steel after nitration, oxidation, and ion irradiation (H+, N+ ),” Fiz. Khim. Obrab. Mater., No. 5, 10–15 (1992).
R. I. Kripyakevich, R. I. Van'kovich, B. F. Kachmar, et al., “Equipment for investigation of the hydrogen permeability of materials,” Fiz.-Khim. Mekh. Mater., 6, No. 4, 72–76 (1970).
P. V. Gel'd and R. A. Ryabov, Hydrogen in Metals and Alloys [in Russian], Metallurgiya, Moscow (1974).
Devices and Equipment for Measurement, Control, and Automation of Production Processes [in Russian], A Catalog of the L'viv Polytechnic Institute, L'viv (1976).
L. I. Gomozov, “A physicochemical approach to a problem of prediction of the vacancy swelling,” in: Structural Materials for Reactors of Thermonuclear Fusion [in Russian], Nauka, Moscow (1988), pp. 187–190.
S. D. Gertsriken and I. Ya. Dekhtyar, Diffusion in Metals and Alloys in a Solid Phase [in Russian], Fizmatgiz, Moscow (1960).
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Fedorov, V.V., Korolyuk, R.I., Zasadnyi, T.M. et al. Hydrogen Permeability of ÉP-838 and Kh12G20V Reactor Steels after Alloying and Thermal Treatment. Materials Science 36, 527–533 (2000). https://doi.org/10.1023/A:1011357904304
Issue Date:
DOI: https://doi.org/10.1023/A:1011357904304