Fission products speciation in nuclear fuel: Synthesis and characterisation of mixed oxide (U,Pu)O2 SIMfuel
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Title
Fission products speciation in nuclear fuel: Synthesis and characterisation of mixed oxide (U,Pu)O2 SIMfuel
Authors
Keywords
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Journal
Journal of Nuclear Materials
Volume 585, Issue -, Pages 154607
Publisher
Elsevier BV
Online
2023-07-18
DOI
10.1016/j.jnucmat.2023.154607
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Note: Only part of the references are listed.- Observable consequences of self-irradiation damage in a MIMAS-type MOX nuclear fuel as analyzed by x-ray diffraction, electron microprobe analysis, and Raman imaging. A possible methodological approach
- (2022) Orhun Kahraman et al. JOURNAL OF APPLIED PHYSICS
- Fission products chemistry in simulated PWR fuel up to 2100°C: Experimental characterisation and TAF-ID modelling
- (2022) E. Geiger et al. JOURNAL OF NUCLEAR MATERIALS
- Simulation of the chemical state of high burnup (U,Pu)O2 fuel in fast reactors based on thermodynamic calculations
- (2020) Karl Samuelsson et al. JOURNAL OF NUCLEAR MATERIALS
- Charge compensation mechanisms in Nd-doped UO2 samples for stoichiometric and hypo-stoichiometric conditions: Lack of miscibility gap
- (2020) Bernardo Herrero et al. JOURNAL OF NUCLEAR MATERIALS
- Determination of the plutonium content and O/M ratio of (U,Pu)O2-x using Raman spectroscopy
- (2020) L. Medyk et al. JOURNAL OF NUCLEAR MATERIALS
- ROBL-II at ESRF: a synchrotron toolbox for actinide research
- (2020) Andreas C. Scheinost et al. JOURNAL OF SYNCHROTRON RADIATION
- TAF-ID: An international thermodynamic database for nuclear fuels applications
- (2020) C. Guéneau et al. CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY
- From Th-Rhabdophane to Monazite-Cheralite Solid Solutions: Thermal Behavior of Nd1–2xThxCaxPO4·nH2O (x = 0–0.15)
- (2019) Danwen Qin et al. CRYSTAL GROWTH & DESIGN
- Aliovalent Cation Substitution in UO2: Electronic and Local Structures of U1–yLayO2±x Solid Solutions
- (2018) Damien Prieur et al. INORGANIC CHEMISTRY
- A review of microstructural features in fast reactor mixed oxide fuels
- (2018) Riley Parrish et al. JOURNAL OF NUCLEAR MATERIALS
- New insight in the uranium valence state determination in U y Nd 1−y O 2±x
- (2018) R. Bès et al. JOURNAL OF NUCLEAR MATERIALS
- Pre- and post-oxidation Raman analysis of (U, Ce)O 2 oxides
- (2018) J.M. Elorrieta et al. JOURNAL OF NUCLEAR MATERIALS
- GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors
- (2018) Marc Lainet et al. JOURNAL OF NUCLEAR MATERIALS
- High-pressure behavior of A2B2O7 pyrochlore (A=Eu, Dy; B=Ti, Zr)
- (2017) Dylan R. Rittman et al. JOURNAL OF APPLIED PHYSICS
- Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample
- (2017) E. Geiger et al. JOURNAL OF NUCLEAR MATERIALS
- Raman study of the oxidation in (U, Pu)O 2 as a function of Pu content
- (2017) J.M. Elorrieta et al. JOURNAL OF NUCLEAR MATERIALS
- Raman microspectroscopic studies of unirradiated homogeneous (U0.76 Pu0.24 )O2+x : the effects of Pu content, non-stoichiometry, self-radiation damage and secondary phases
- (2017) Zeynep Talip et al. JOURNAL OF RAMAN SPECTROSCOPY
- Multiscale structural characterizations of mixed U(iv)–An(iii) oxalates (An(iii) = Pu or Am) combining XAS and XRD measurements
- (2016) B. Arab-Chapelet et al. DALTON TRANSACTIONS
- Actinide Oxidation State and O/M Ratio in Hypostoichiometric Uranium–Plutonium–Americium U0.750Pu0.246Am0.004O2–x Mixed Oxides
- (2016) Romain Vauchy et al. INORGANIC CHEMISTRY
- Insights on fission products behaviour in nuclear severe accident conditions by X-ray absorption spectroscopy
- (2016) E. Geiger et al. JOURNAL OF NUCLEAR MATERIALS
- Water-gas shift: Characterization and testing of nanoscale YSZ supported Pt catalysts
- (2015) Michela Martinelli et al. APPLIED CATALYSIS A-GENERAL
- Ceramic processing of uranium–plutonium mixed oxide fuels (U1−yPuy)O2 with high plutonium content
- (2014) Romain Vauchy et al. CERAMICS INTERNATIONAL
- X-ray absorption spectroscopy investigations on radioactive matter using MARS beamline at SOLEIL synchrotron
- (2014) Isabelle LLorens et al. RADIOCHIMICA ACTA
- Controlling the oxygen potential to improve the densification and the solid solution formation of uranium–plutonium mixed oxides
- (2013) Ségolène Berzati et al. JOURNAL OF NUCLEAR MATERIALS
- XANES and EXAFS study of the local order in nanocrystalline yttria-stabilized zirconia
- (2013) O. J. Dura et al. PHYSICAL REVIEW B
- Determination of in-depth damaged profile by Raman line scan in a pre-cut He2+ irradiated UO2
- (2012) G. Guimbretière et al. APPLIED PHYSICS LETTERS
- Raman spectroscopy of plutonium dioxide and related materials
- (2012) Mark J. Sarsfield et al. JOURNAL OF NUCLEAR MATERIALS
- Fiji: an open-source platform for biological-image analysis
- (2012) Johannes Schindelin et al. NATURE METHODS
- Characterization of radioactive materials using the MARS beamline at the synchrotron SOLEIL
- (2011) Bruno Sitaud et al. JOURNAL OF NUCLEAR MATERIALS
- Experimental Insight into the Radiation Resistance of Zirconia-Based Americium Ceramics
- (2009) Renaud C. Belin et al. INORGANIC CHEMISTRY
- Evidence for a double doping regime in Nd:YAG nanopowders
- (2009) Marco Giorgetti et al. JOURNAL OF MATERIALS SCIENCE
- Solubility of ThO2 in Gd2Zr2O7 pyrochlore: XRD, SEM and Raman spectroscopic studies
- (2009) B.P. Mandal et al. JOURNAL OF NUCLEAR MATERIALS
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