Multiphysics thermo-mechanical behavior modeling for annular uranium-plutonium mixed oxide fuels in a lead-cooled fast reactor

Autor: Yutai Cai, Ken Chen, Wenzhong Zhou, Long Gu

Publikováno v: Frontiers in Energy Research, Vol 10 (2022)

Understanding and predicting nuclear fuel behavior is the cornerstone for fuel design and optimization, and the safe and economic operation of nuclear reactors. Due to the excellent neutronic economy and safe operational characteristics of lead/lead-

Externí odkaz: https://doaj.org/article/f59272c8752a40d6b81f9d9e812a1af2

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Stability of zinc stearate under alpha irradiation in the manufacturing process of SFR nuclear fuels

Autor: Xavier Colin, Jackie Vermeulen, Fabienne Audubert, Laurent Venault, D. Baux, J. Gracia, T. Sauvage

Publikováno v: Radiation Physics and Chemistry
Radiation Physics and Chemistry, Elsevier, 2018, 144, pp.92-99. ⟨10.1016/j.radphyschem.2017.10.020⟩
Radiation Physics and Chemistry, 2018, 144, pp.92-99. ⟨10.1016/j.radphyschem.2017.10.020⟩

International audience; The manufacture of new fuels for sodium-cooled fast reactors (SFRs) will involve powders derived from recycling existing fuels in order to keep on producing electricity while saving natural resources and reducing the amount of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00ff823688ccbdf464c3be0cf92701c0
https://doi.org/10.1016/j.radphyschem.2017.10.020

Towards validation of criticality calculations for systems with MOX powders

Autor: Veronique Rouyer, Tatiana Ivanova, Anatoly Tsiboulia, Yevgeniy Rozhikhin

Publikováno v: Annals of Nuclear Energy
Annals of Nuclear Energy, 2009, 36 (3), pp.305-309. ⟨10.1016/j.anucene.2008.12.018⟩

A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at IPPE, Russia. The program was designed to provide a basis for validation of criticality calculations for MOX fuel manufacturing processes and particula

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::169e1eb49df02e98409e0f312ed5470e
https://doi.org/10.1016/j.anucene.2008.12.018

Etude des équilibres de phases en fonction de la température dans le système UO2-PuO2-Pu2O3 pour les céramiques nucléaires aux fortes teneurs en plutonium

Autor: Truphemus, Thibaut

Dans la section UO2-PuO2-Pu2O3, les équilibres de phases décrivent un domaine monophasé (U1-y,Puy)O2-x stable pour y
In the UO2-PuO2-Pu2O3 section, a monophasic (U1-y,Puy)O2-x domain is stable for y

Externí odkaz: http://www.theses.fr/2013AIXM4303/document