Manufacturing LEU-foil annular target in Brazil

Author(s)

Durazzo, Michelangelo ^[1] ; Souza, Jose A. B. ^[1] ; Ianelli, Ricardo F. ^[1] ; Takara, Eriki M. ^[1] ; Neto, Jose S. Garcia ^[1] ; Saliba-Silva, Adonis M. ^[1] ; Urano de Carvalho, Elita F. ^[1]

Affiliation

^[1] IPEN CNEN SP, Nucl & Energy Res Inst, Sao Paulo - Brazil

• Document type: Journal article
• Source: ANNALS OF NUCLEAR ENERGY; v. 165, JAN 2022.
• Web of Science Citations: 0

Abstract

Molybdenum-99 is the most important isotope because its daughter isotope, technetium-99m, has been the most used medical radioisotope. The primary method used to produce Mo-99 derives from the fission of U-235 incorporated in so-called irradiation targets. Two routes are being developed to make Mo-99 by fissioning with low enriched uranium (LEU) fuel. The first adopts UAlx-Al dispersion plate targets. The second uses uranium metal foil annular targets. The significant advantage of uranium foil targets over UAlx-Al dispersion targets is the high density of uranium metal. This work presents the experience obtained in the development of the uranium metal annular target manufacturing steps. An innovative method to improve the procedure for assembling the uranium foil on the tubular target was presented. The experience attained will help the future production of Mo-99 in Brazil through the target irradiation in the Brazilian Multipurpose Reactor (RMB). (c) 2021 Elsevier Ltd. All rights reserved. (AU)

• FAPESP's process: 15/08922-0 - Development of the fabrication procedures for manufacturing metallic uranium foil targets for Mo-99 production by nuclear fission
• Grantee: Michelangelo Durazzo
• Support Opportunities: Regular Research Grants
• FAPESP's process: 18/18228-1 - RERTR-2018 International Meeting on Reduced Enrichment for Research and Test Reactors
• Grantee: Michelangelo Durazzo
• Support Opportunities: Research Grants - Meeting - Abroad