Title: Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors.
Authors: Savchenko, A. M.; Konovalov, Y. V.; Kulakov, G. V.; Tarasov, B. A.; Ershov, S. A.; Mainikov, E. V.; Bubenschikov, D. A.
Abstract: In order to use reduced enrichment fuel and increase the burnup of fuel elements in research reactors, metal-ceramic alloys based on uranium-molybdenum superalloys are being developed. The alloy structure is based on a γ-phase, which also contains ceramic (intermetallic) phases. Having the highest density of uranium, compatibility with aluminum, high radiation resistance, and low molybdenum content, these phases precipitate along grain boundaries, which allows fuel particles to be obtained by crushing. This fits into the existing technology. The use of such fuel will make it possible to manufacture and supply reduced enrichment fuel (fuel elements) with increased uranium density and performance to research reactors without increasing costs.
Subjects: NUCLEAR fuel elements; RESEARCH reactors; CRYSTAL grain boundaries; HEAT resistant alloys; URANIUM; MOLYBDENUM
Publication: Atomic Energy, 2024, Vol 136, Issue 3/4, p151
ISSN: 1063-4258
Publication type: Academic Journal
DOI: 10.1007/s10512-024-01145-0

Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors.

Savchenko, A. M.; Konovalov, Y. V.; Kulakov, G. V.; Tarasov, B. A.; Ershov, S. A.; Mainikov, E. V.; Bubenschikov, D. A.