Search Results - "WISS, T"
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1
Synthesis of Reactive Telechelic Polymers Based on Pentafluorophenyl Esters
Published in Macromolecules (25-11-2008)“…A diazo initiator and a chain transfer agent (CTA), both containing a pentafluorophenyl (PFP) activated ester, were synthesized. In a RAFT polymerization using…”
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2
Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy
Published in Journal of nuclear materials (01-10-2017)“…Scanning acoustic microscopy is a non-destructive technique that allows determining the local material elastic properties by measuring the velocity of acoustic…”
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3
Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour
Published in Journal of nuclear materials (01-01-2021)“…•SIMS and TEM techniques were combined to compare the thermal behaviour of Cs and Xe in UO2.•Both elements form bubbles with different growth kinetics.•At…”
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4
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
Published in Nuclear engineering and design (15-12-2018)“…•Review of all the available experimental results for Henry’s constant of helium in oxide nuclear fuel.•Clustering of data based on microstructure of measured…”
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5
Effect of molybdenum on the behaviour of caesium in uranium dioxide at high temperature
Published in Journal of nuclear materials (01-03-2021)“…•The effect of a metallic fission product on Cs behaviour and its release in UO2 was investigated as a relevant aspect of fuel safety•Mo and Cs were…”
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6
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations
Published in Nuclear engineering and design (15-04-2018)“…•Review of all the available experimental data of helium diffusivity in oxide nuclear fuel.•Clustering of the data based on the experimental technique used to…”
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7
Melting behaviour of uranium-americium mixed oxides under different atmospheres
Published in The Journal of chemical thermodynamics (01-01-2020)“…•The very high melting temperatures of (U,Am)-oxides (T > 2500 K) were measured.•The effect of the oxidation on the melting behaviour was studied.•Extensive…”
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8
Elastic properties of severely degraded fuels
Published in Journal of nuclear materials (01-02-2020)“…The decommissioning of nuclear power plants subjected to a nuclear accident is a crucial activity for post-accident recovery and remediation of the affected…”
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9
TEM analysis of irradiation-induced interaction layers in coated UMo/X/Al trilayer systems (X= Ti, Nb, Zr, and Mo)
Published in Journal of nuclear materials (01-02-2018)“…Uranium-molybdenum (UMo) alloy powder embedded in an Al matrix is considered as a promising candidate for fuel conversion of research reactors. A modified…”
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10
High Frequency Acoustic Microscopy for the Determination of Porosity and Young's Modulus in High Burnup Uranium Dioxide Nuclear Fuel
Published in IEEE transactions on nuclear science (01-06-2016)“…During irradiation UO 2 nuclear fuel experiences the development of a non-uniform distribution of porosity which contributes to establish varying mechanical…”
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11
Ring-Opening Polymerization and Copolymerization of Propylene Oxide Catalyzed by N-Heterocyclic Carbenes
Published in ChemCatChem (01-02-2014)“…Herein, we demonstrate the application of adducts of various N‐heterocyclic carbenes (NHCs) with CO2 (i.e., NHC–CO2) as precatalysts in the ring‐opening…”
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12
Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen
Published in Journal of nuclear materials (01-07-2008)“…A commercial PWR fuel sample with a local burn-up of about 240MWd/kgHM was annealed in a Knudsen cell mass spectrometer system with a heating rate of 10K/min…”
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13
Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
Published in Journal of nuclear materials (01-10-2016)“…During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fuel. Their quantification is important to evaluate their…”
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14
Thermal diffusion of helium in 238Pu-doped UO2
Published in Journal of nuclear materials (01-02-2014)“…UO2 samples doped with 0.1wt.% plutonium oxide have been investigated with the aim to study alpha-damage effects and the behaviour of radiogenic helium in…”
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15
Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy
Published in JOM (1989) (01-12-2012)“…Recent electron microscopy investigations are presented with an emphasis on properties related to the safe extended operation of nuclear fuel. In particular,…”
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16
TEM-EELS analyses of protactinium
Published in Materials research express (01-02-2019)“…A fragment of metallic protactinium (Pa) has been studied using a transmission electron microscope (TEM) equipped with an electron energy loss spectroscopy…”
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17
Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels
Published in Journal of nuclear materials (01-02-2010)“…The effect of α-damage on the thermophysical properties of UO 2 was investigated using samples doped with 238Pu. Characterisations were performed after…”
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18
The mechanism of the hydrothermal alteration of cerium- and plutonium-doped zirconolite
Published in Journal of nuclear materials (01-03-2011)“…A comprehensive study on the aqueous stability of Ce- and Pu-doped zirconolite has been performed. Four series of hydrothermal experiments were carried out…”
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19
Fission product release and microstructure changes of irradiated MOX fuel at high temperatures
Published in Journal of nuclear materials (01-11-2013)“…Samples of irradiated MOX fuel of 44.5GWd/tHM mean burn-up were prepared by core drilling at three different radial positions of a fuel pellet. They were…”
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20
Uranium secondary phase formation during anoxic hydrothermal leaching processes of UO2 nuclear fuel
Published in Journal of nuclear materials (15-05-2005)“…Mobilisation of uranium in geologic environments from UO2 solid phases usually takes place by oxidative dissolution involving a change of U oxidation state…”
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