Manufacturing high-uranium-loaded dispersion fuel plates in Brazil

Author:

Durazzo Michelangelo,Souza Jose Antonio Batista,Urano de Carvalho Elita Fontenele,Restivo Thomaz Augusto Guisard,Genezini Frederico Antonio,Leal Neto Ricardo Mendes

Funder

Fundação de Amparo à Pesquisa do Estado de São Paulo

National Council for Scientific and Technological Development

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference40 articles.

1. Nuclear Energy Agency, 2019. The Supply of Medical Radioisotopes: 2019 Medical Isotope Demand and Capacity Projection for the 2019-2024 Period. OECD Publishing, Paris, 2019. NEA/SEN/HLGMR(2019)1 (available at https://www.oecd-nea.org/med-radio/docs/sen-hlgmr2019-1.pdf).

2. Balart, S., Bruzzoni, P., Granovsky, M., Gribaudo, L., Hermida, J., Ovejero, J., Rubiolo, G., Vicente, E., 2000. U-Mo alloy powder obtained by a hydride-dehydride process: in Proceedings of the 2000 International Meeting on Reduced Enrichment for Research and Test Reactors, Las Vegas, Nevada, October 1-6, 2000. (available at https://www.osti.gov/etdeweb/servlets/purl/20432977).

3. Beaver, R. J., Patriarca, P., Adamson, G. M., 1964. Procedures for fabricating aluminum-base ATR fuel elements. Oak Ridge, Tennessee, 1964. ORNL-3632.

4. Billington, D. S., 1955. Radiation damage in reactor materials: in Proceedings of the International Conference on the Peaceful Uses of Atomic Energy, Geneve, Switzerland, August 8-20, 1955.Paper No. P/744.

5. Burkes, D. E., Mickum, G. S., Wachs, D. M., 2010. Thermophysical properties of U-10Mo alloy. Idaho National Laboratory, Idaho Falls, Idaho, November 2010. INL/EXT-10-19373. (available at https://inldigitallibrary.inl.gov/sites/sti/sti/4702554.pdf).

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