Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design

The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented. Attention is focused mainly on the development of fuel assemblies with fuel based on UO 2 + Al, U 3 Si 2 + Al, and U9%Mo + Al for the LVR-15 rese...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) Vol. 129; no. 4; pp. 234 - 236
Main Authors: Cherepnin, Yu. S., Pulinets, A. A., Kravtsova, O. A., Simonidi, A. R., Chizhova, E. S., Larionov, I. A., Logvenchev, S. I.
Format: Journal Article
Language:English
Published: New York Springer US 01-02-2021
Springer
Springer Nature B.V
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Summary:The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented. Attention is focused mainly on the development of fuel assemblies with fuel based on UO 2 + Al, U 3 Si 2 + Al, and U9%Mo + Al for the LVR-15 research reactor (Czech Republic). A design-basis validation is given for IRT-4M fuel assemblies with fuel composition based on UO 2 + Al and U 3 Si 2 + Al, IRT-3M fuel assemblies with a fuel composition based on U9%Mo + Al, and IRT-P fuel assemblies with a fuel composition based on U 3 Si 2 + Al and UO 2 + Al. In substantiation of the operability and confirmation of the hydraulic characteristics of the IRT-P fuel assembly, which is equipped with 21 fuel rods, manufactured at NZKhK, there are plans to manufacture and conduct hydraulic testing of a full-scale model.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-021-00740-9