Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy

Wiss, T.; Thiele, H.; Janssen, André; Papaioannou, D.; Rondinella, V.V.; Konings, R.J.M.

doi:10.1007/s11837-012-0483-1

Cited by 38 publications

(22 citation statements)

References 19 publications

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“…Spent nuclear fuel (SNF) undergoes significant chemical and microstructural changes during reactor operations. [3][4][5][6][7][8] Some fission products are retained within the UO 2 matrix in solid solution, while at the same time the noble gases-xenon (Xe) and krypton (Kr)-and the 4d group metals-molybdenum (Mo), technetium (Tc), ruthenium (Ru), rhodium (Rh), and palladium (Pd)-are trapped as gas bubbles and partitioned into metallic phases, respectively. [9][10][11][12][13][14] This metallic phase has gone by several names in the literature, including white inclusions, 15,16 fission-product alloy, 16 5-metal particles, 17 epsilon particles, 18,19 and noble metal phase.…”

Section: Introductionmentioning

confidence: 99%

Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel

et al. 2020

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We have made observations of noble metal phase fission-product agglomerates and gaseous xenon within the fuel-cladding interaction (FCI) zone of a high-burnup UO 2 fuel. The FCI is the boundary between the UO 2 pellet outer surface and the inner wall of the oxidized Zr-liner/cladding of the fuel rod. These fission-product agglomerates are well known to occur within the spent fuel matrix, and although radionuclides have been reported by others, we reveal aspects of their speciation and morphology. That they occur as discrete particles in the oxidized Zr liner, suggests the occurrence of hitherto unknown processes in the FCI zone during reactor operation, and this may have implications for the long-term storage and disposal of these types of materials. As expected, the particle agglomerates, which ranged in size from the nanometer scale to the micrometer scale, contained mainly Mo, Ru, Tc, Rh, and Pd; however, we also found significant quantities of Te associated with Pd. Indeed, we found nanometer scale separation of the distinct Pd/Te phase from the other fission products within the particles. Often associated with the particles was concentrations of uranium, sometimes appearing as a "cloud" with a tail emanating from the fuel into the oxidized cladding liner. Many of the noble metal phase particles appeared as fractured clusters separated by Xe-gas-filled voids. Possible mechanisms of formation or transport in the cladding liner are presented.

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Section: Introductionmentioning

confidence: 99%

Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel

et al. 2020

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“…The investigations have been performed on a FEI Tecnai G 2 TEM, equipped with a GATAN Tridiem GIF camera, an EDAX energy dispersive X-ray analysis system, a tomography suite and a HAADF (High-Angle Annular Dark Field) detector for the STEM (Scanning Transmission Electron Microscopy) imaging. The TEM has been adapted for the examination of highly active or irradiated nuclear materials thanks to a flange that has been inserted in the octagon hosting the objective lenses, and a glove box mounted on this flange around the compustage [11]. Thus, the sample can be moved from the glove box where it was prepared to the microscope making use of a La Calhène DPTE® system.…”

Section: Methodsmentioning

confidence: 99%

Investigation on the use of Americium Oxide for Space Power Sources: Radiation Damage Studies

et al. 2017

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Within Europe 241 Am is a feasible alternative to 238 Pu that can provide a heat source for radioisotope thermoelectric generators (RTGs) and radioisotope heating units (RHUs) to be used in Electrical power sources used in outer planet missions. In the EPSO-SPACE* project developed as an exploratory research at JRC, a new type of nuclear power source, to provide heat and electricity for deep space missions is considered. It will consist of a 241 Am based compound with aerogel thermal insulation and thermocouples in close contact with the heat source. The assembly is inside an iridium encapsulation to withstand all relevant accident scenarios. The design will be modular and combinable for required electrical output. Several candidate Americium compounds will be investigated for chemical stability at high temperature and for self-irradiation damage. New thermo-electric converter materials containing actinides will be assessed, and a robust encapsulation designed. Safety analyses will be performed including launch explosion and re-entry accidents. The research will conclude in a conceptual design of a prototype power source. In the first part of this study, americium dioxide will be considered from the point of view of its chemical durability and of its behavior against radiation damage and helium formation, two aspects to be carefully investigated due to the high alpha-activity of the americium. Transmission electron Microscopy (TEM) and helium thermal desorption spectrometry (TDS) experiments will be described and results on aged (more than 30 years) AmO 2 reported. Some comparison with 238 PuO 2 based RTG's will be discussed.

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“…Transmission electron microscopy (TEM) investigations were performed with a FEI Tecnai G2 F20 XT specially modified for the analyses of radioactive materials [36]. The TEM operates at 200 kV and is equipped with a Gatan GIF Tridiem camera, an additional Gatan slow scan camera, and an EDAX EDS Genesis System.…”

Section: Methodsmentioning

confidence: 99%

The dissolution of helium in La-doped UO2 as a surrogate of hypo-stoichiometric UO2

Talip

Wiss

Janssen

et al. 2015

Nuclear Materials and Energy

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In this work, the dissolution of helium in La-doped UO 2 samples was studied by helium infusion in an autoclave followed by thermal desorption (laser heating) coupled to mass spectrometer systems for the determination of helium release rate and the total helium quantity. Lanthanum was chosen as a dopant in UO 2 to study the effect of hypo-stoichiometry on helium solubility together with the impurity effect. Comparison of the dissolved He quantity from the samples with different La content showed that the dissolved He quantity slightly increases with increasing oxygen vacancy concentration in the samples.

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Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy

Cited by 38 publications

References 19 publications

Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel

Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel

Investigation on the use of Americium Oxide for Space Power Sources: Radiation Damage Studies

The dissolution of helium in La-doped UO2 as a surrogate of hypo-stoichiometric UO2

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