Journals →  Tsvetnye Metally →  2022 →  #10 →  Back

ArticleName Compatibility of U – Mo and V – Ti – Cr аlloys at 900 oC
DOI 10.17580/tsm.2022.10.05
ArticleAuthor Nikitin S. N., Tarasov B. A., Shornikov D. P., Yurlova A. S.

National Research Nuclear University MEPhI, Moscow, Russia:

S. N. Nikitin, Lead Engineer at the Sectoral Research & Development Lab 709, e-mail:
B. A. Tarasov, Principal Specialist at the Institute of Industrial Nuclear Technology, Candidate of Technical Sciences, e-mail:
D. P. Shornikov, Associate Professor at the Department of Physical Problems of Materials Science, Candidate of Technical Sciences, e-mail:
A. S. Yurlova, Engineer at the Central Radiation Safety Service of the Nuclear Centre, e-mail:


Metallic fuel has long served as a common nuclear fuel. The Generation IV Reactors programme considers metallic fuel feasible for Generation IV reactors due to its unique physico-chemical characteristics. In spite of all the advantages offered by metallic nuclear fuel (such as density and heat conductivity), there are certain factors limiting its use. The main factors include fuel swelling and interaction with steel cladding. The problem of swelling can be resolved by lowering the smeared density of nuclear fuel to 75% of theoretical values, which can be achieved by reducing the section of the fuel column and opening the fuel-cladding gap. An optimal solution would be to use porous fuel, the theoretical density of which is 75%. The problem of metallic fuel-steel cladding interaction is caused by a uranium-iron eutectic. One of the alternatives could be to start using vanadium alloys (V – Ti – Cr) for claddings as their eutectic interaction with uranium starts at higher temperatures. The authors carried out an experiment to understand how V – 4Ti – 4Cr alloys would interact with U10Mo alloys. The experiment was conducted at the temperature of 900 oC for 11 hours. A slight interdiffusion of the components was observed, and a high degree of similarity between vanadium alloys and oxygen and nitrogen was noted.

keywords Diffusion, interaction layer, vanadium alloys, uranium-molybdenum alloy, metallic fuel, fuel-cladding interaction

1. Abram T. A technology roadmap for generation-IV nuclear energy systems. USDOE/GIF-002-00, 2002. 97 p.
2. Shornikov D. P., Baranov V. G., Nikitin S. N., Tarasov B. A. Application of powder metallurgy for metal nuclear fuel manufacturing. Tsvetnye Metally. 2015. No. 10. pp. 85–89. DOI: 10.17580/tsm.2015.10.15.
3. Nikitin S. N., Tarasov B. A., Shornikov D. P., Baranov V. G. Influence of a doping by Al stainless steel on kinetics and character of interaction with the metallic nuclear fuel. IOP Conference Series: Materials Science and Engineering. 2016. Vol. 130, No. 1. 012024.
4. Nikitin S. N., Tarasov B. A., Shornikov D. P., Baranov V. G. Increasing of compatibility of metallic nuclear fuel with various construction materials. Tsvetnye Metally. 2015. No. 3. pp. 36–39. DOI: 10.17580/tsm.2015.03.08.
5. Chakraborty S., Choudhuri G., Banerjee J., Agarwal R., Kumar A. Fuel clad chemical interaction of U – Mo fast reactor fuel. Journal of Nuclear Materials. 2019. Vol. 516. pp. 1–10.

6. Fukumoto K., Miura S., Yamazaki M., Satou M. Effect of temperature history on the irradiation behavior of vanadium alloy irradiated with the MARICO-II rig in a fast reactor, JOYO. Nuclear Materials and Energy. 2022. Vol. 30, No. 101153.
7. Fukumoto K., Fujita K., Saito H., Sekio Y., Yamazaki M. Effect of temperature history on swelling behavior of V – Fe binary alloy irradiated in a fast reactor Joyo. Nuclear Materials and Energy. 2020. Vol. 24, No. 100760.
8. Ditenberg I. A., Smirnov I. V., Grinyaev K. V., Chernov V. M., Potapenko M. M.Microstructure and mechanical properties of V – Cr – Zr alloy with carbide and oxide strengthening. Materials Science and Engineering A. 2022. Vol. 843, No. 143159.
9. Smith J. F. Phase diagrams of binary vanadium alloys. ASM, 1989. 329 p.
10. Vol A. E. The structure and properties of binary metallic systems. Vol. 2. Moscow : Fizmatgiz, 1962. 962 p.
11. Nikulin S. A., Votinov S. N., Rozhnov A. B. Vanadium alloys for nuclear power industry. Moscow : NITU MISiS, 2014. 206 p.
12. Muroga T., Nagasaka T., Abe K., Chernov V.M., Matsui H. et al. Vanadium alloys – Overview and recent results. Journal of Nuclear Materials. 2002. Vol. 307-311, Part 1. pp. 547–554.
13. Smith D. L., Loomis В. A., Diercks D. R. Vanadium-base alloys for fusion reactor applications — A review. Journal of Nuclear Materials. 1985. Vol. 135. pp. 125–140.
14. Gurov K. P., Kartashkin B. A., Ugaste Yu. E. Interdiffusion in multiphase metallic sy stems. Moscow : Nauka, 1981. 350 p.
15. Kittel J. H., Ayer J. E., Beck W. N., Brodsky M. B., O’Boyle D. R. et al. Plutonium and plutonium alloys as nuclear fuel materials. Nuclear Engineering and Design. 1971. Vol. 15. pp. 373–440.
16. Tarasov B. A., Osintsev A. V., Savelyev M. D., Konovalov I. I. Short-term mechanical properties of Fe – Cr – Al – Si alloys. KnE Materials Science. 2018. Vol. 4, No. 1. pp. 491–497.

Language of full-text russian
Full content Buy