Poster

FZJ-2014-03822

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Fabrication of simulated minor actinide containing fuel particles and analytical characterization methods

Schreinemachers, C. (Corresponding Author)FZJ* ; Middendorp, R.FZJ* ; Bukaemskiy, A.FZJ* ; Klinkenberg, M.FZJ* ; Neumeier, S.FZJ* ; Modolo, G.FZJ* ; Bosbach, D.FZJ*

2014

Please use a persistent id in citations: http://hdl.handle.net/2128/5841

Abstract: Partitioning and transmutation (P&T) is a promising method to safely handle minor actinides which origin from energy production by nuclear fission. In this concept, actinide co-conversion processes play an important role to close the fuel cycle. During the heterogeneous recycling of minor actinides, oxidic materials containing uranium as main matrix are used as innovative nuclear fuel.The focus of our research is on the fabrication of simulated fuel particles. A dustless preparation method is the sol-gel route via internal gelation (IG) [1], where an aqueous colloidal solution is transformed into a solid particle. Another promising concept is the weak-acid resin process (WAR) [2]. During this process, weak-acid cation exchange resins are loaded with ions.In this work, both methods were used to fabricate microspheres consisting of a homogeneous mixture of U and Nd. Neodymium acts as a surrogate for trivalent actinides, such as americium. Mass and size characteristics of the particles prepared by IG have been studied. Finally, the particles were sintered in a reducing atmosphere and the products have been investigated by SEM/EDX and XRD.In order to investigate simulated fuel particles prepared by the WAR, the ion exchange resins Amberlite IRC-86 and Lewatit TP-207 were loaded with UO22+ and Nd3+. Various parameters have been investigated to maximize the adsorption. A thermal treatment has been carried out and the products were analyzed by SEM/EDX and XRD.[1] J. L. Collins et al. , Radiochim. Acta, 1987, 42: p. 121–134[2] K. Notz et al., Radiochim. Acta, 1978, 25: p. 153-160

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Contributing Institute(s):

1. Nukleare Entsorgung und Reaktorsicherheit (IEK-6)

Research Program(s):

1. 142 - Safety Research for Nuclear Waste Disposal (POF2-142) (POF2-142)
2. ASGARD - Advanced fuelS for Generation IV reActors: Reprocessing and Dissolution (295825) (295825)
3. HITEC - Helmholtz Interdisciplinary Doctoral Training in Energy and Climate Research (HITEC) (HITEC-20170406) (HITEC-20170406)

Appears in the scientific report 2014

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Database coverage:

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