Processing and Composition Control of Weak-Acid-Resin-Derived Fuel Microspheres

Weber, G. W.; Beatty, R.L.; Tennery, V.J.

doi:10.13182/nt77-a31881

Cited by 19 publications

(9 citation statements)

References 1 publication

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“…9 Aiming at the construction of dedicated facilities to supply reactor needs, such as ASTRID, the development of an innovative route using micronic spherical precursors is studied. Through an adaptation of the weak acid resin (WAR) process, [10][11][12][13] the general approach consists of elaborating micronic and brittle spherical mixed-oxide precursors from ion exchange resin microspheres. These nanostructured soft agglomerates were developed to have the advantages of nano-powders, i.e., high reactivity during the sintering step, without the major drawback of nanometric pulverulent compounds, i.e., high dissemination capability during handling.…”

Section: Introductionmentioning

confidence: 99%

In situ characterization of uranium and americium oxide solid solution formation for CRMP process: first combination of in situ XRD and XANES measurements

et al. 2015

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Transmutation of americium in heterogeneous mode through the use of U1-xAmxO2±δ ceramic pellets, also known as Americium Bearing Blankets (AmBB), has become a major research axis. Nevertheless, in order to consider future large-scale deployment, the processes involved in AmBB fabrication have to minimize fine particle dissemination, due to the presence of americium, which considerably increases the risk of contamination. New synthesis routes avoiding the use of pulverulent precursors are thus currently under development, such as the Calcined Resin Microsphere Pelletization (CRMP) process. It is based on the use of weak-acid resin (WAR) microspheres as precursors, loaded with actinide cations. After two specific calcinations under controlled atmospheres, resin microspheres are converted into oxide microspheres composed of a monophasic U1-xAmxO2±δ phase. Understanding the different mechanisms during thermal conversion, that lead to the release of organic matter and the formation of a solid solution, appear essential. By combining in situ techniques such as XRD and XAS, it has become possible to identify the key temperatures for oxide formation, and the corresponding oxidation states taken by uranium and americium during mineralization. This paper thus presents the first results on the mineralization of (U,Am) loaded resin microspheres into a solid solution, through in situ XAS analysis correlated with HT-XRD.

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Section: Introductionmentioning

confidence: 99%

In situ characterization of uranium and americium oxide solid solution formation for CRMP process: first combination of in situ XRD and XANES measurements

et al. 2015

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“…The ion exchange Weak Acid Resin (WAR) process was initially used for the production of carbide kernels for High Temperature Reactor particle fuels [32], [33]. The WAR flowchart has been revisited and adapted to oxide fuels [34] up to the synthesis of (U,Am)O 2 beads and pellets [35].…”

Section: Adaptation Of the Weak Acid Resin Processmentioning

confidence: 99%

Outcomes of the PELGRIMM project on Am-bearing fuel in pelletized and spherepac forms

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Béjaoui

et al. 2018

Journal of Nuclear Materials

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The PELGRIMM project was a FP7-European project carried out from 2012 to 2017. It was devoted to the investigation of spherepacked and pelletized fuel forms for Minor Actinide transmutation in homogeneous and heterogeneous recycling modes. PELGRIMM aimed at constituting a new step in the long term process in the assessment of Minor Actinide-bearing fuel, initiated within the European projects ACSEPT, F-BRIDGE, CP-ESFR and FAIRFUELS. The present paper provides an overview of the main technical outcomes gained within PELGRIMM. The developments of alternative processes in order to simplify synthesis routes and to limit secondary waste streams for Minor Actinide-bearing fuel preparation are detailed. The first results of behaviour under irradiation of spherepacked and pelletized fuel forms are provided from Post-Irradiation Examinations on (U,Pu,Am)O 2 and (U,Am)O 2 fuels respectively irradiated during SPHERE and MARIOS experiments, along with the description of the latest irradiation experiment, MARINE. In parallel, the capabilities of existing models and calculation codes have been improved to describe

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“…Results of metallographic examination on GA TRISO-coated Th02, l:l(Th,U)02, and UCxOy tested in HRB-15B 5-57 5-5. GA particle samples tested in HRB-15B submitted for IMGA analysis at ORNL 5-58 [5][6]. Comparison of gamma-scan results with autoradiography of HRB-15B graphite trays 5-59 5-7.…”

Section: Disclaimermentioning

confidence: 99%

“…The buffer layers in many examined TRISO particles showed irradiationinduced shrinkage, particularly the higher exposure samples. This shrinkage was evidenced by the buffer separating from the inner pyrolytic carbon (IPyC) coating (5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17) and actual cracking and separation within the buffer layer itself ( Fig. 5-19).…”

Section: -6mentioning

confidence: 99%