An attempt to reproduce high burn-up structure by ion irradiation of SIMFUEL

Баранов, В. Г.; Lunev, Artem; Reutov, V. F.; Tenishev, A. V.; Isaenkova, Margarita; Khlunov, A. V.

doi:10.1016/j.jnucmat.2014.04.002

Cited by 13 publications

(5 citation statements)

References 23 publications

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“…Here we focus on ion irradiation studies aimed at investigating the formation mechanisms responsible for the formation of the HBS [510,514,515,516,517]. There are two broad groups of theories for the formation of the HBS [6].…”

Section: Restructured Grain Boundariesmentioning

confidence: 99%

“…Here we focus on ion irradiation studies aimed at investigating the mechanisms responsible for the formation of HBS. ,− There are two broad groups of theories regarding the formation of HBS . The first involves nucleation and growth at either highly defective sites (e.g., dislocation tangles) or amorphous regions near fission tracks.…”

Section: Crystalline Defect Generation Evolution and Characterizationmentioning

confidence: 99%

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Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts seek solid fuels that must withstand unprecedented temperature and radiation extremes. In these advanced fuels, thermal energy transport under irradiation is directly related to reactor performance as well as reactor safety. The science of thermal transport in nuclear fuel is a grand challenge due to both computational and experimental complexities. Here, we provide a comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO2), and one advanced fuel candidate material, thorium dioxide (ThO2). In both materials, 5Concluding Remarks .

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Section: Restructured Grain Boundariesmentioning

confidence: 99%

Section: Crystalline Defect Generation Evolution and Characterizationmentioning

confidence: 99%

Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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“…X-ray diffraction (XRD) analysis was performed on a Bruker D8 Discover diffraction system to study the texture and structural parameters of the compacts and raw powder. XRD patterns were analyzed with the widely used Warren-Averbach approach [15,16] to extract the value of micro-strain ε and the size of coherent scattering regions (CSR) D CSR , in the same way as it was done in [17]. Assuming both screw and edge dislocations are present in the material, the procedure for calculating dislocation density is then straightforward according to the formula:…”

Section: Defect and Diffusion Forum Vol 375mentioning

confidence: 99%

On Morphological and Microstructural Changes in Uranium Dioxide Powder during Binder-Free Hot Pressing

Lunev

Zazolin

Pchelyakov

et al. 2017

DDF

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Plasticity of oxide fuel based on uranium dioxide is one of the less-covered topics in nuclear materials science. A useful tool to study the deformation mechanisms in this material at elevated temperatures is hot pressing. In this work, UO$_{2.06}$ powder prepared via~ADU route was uniaxially compacted at temperatures within the~$250$--$600$~{\textdegree}C range under a compressive axial stress from~$95$ to~$220$~MPa applied for a time interval between~$10$ and~$60$~min. Examinations performed with scanning electron microscopy~(SEM) and density measurements revealed a temperature effect on densification when increasing the compaction temperature from~$400$ to~$600$~\textdegree{C} with other conditions being equal. By varying the loading duration for hot pressing at~$600$~{\textdegree}C under constant compressive stress~$95$~MPa, different stages of compactions were analyzed. In addition,~XRD measurements revealed a texture developing in the material during compaction and a possible increase in dislocation density. It is argumented that dislocation-mediated plasticity contributes to densification at elevated temperatures.

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“…One of the primary motivations behind using SIMFUEL systems is to explore radiation effects on SNF ceramics, whether by ion irradiation [40] or exposure to γ flux [13] in an effort to simulate the highly complex interactions between various highly intense radiation fluxes and ceramic materials which occur within a reactor without resorting to the aforementioned, highly radioactive, neutron irradiated SNF [41]. In other words, the study of these radiation effects combines:…”

Section: Introductionmentioning

confidence: 99%

“…In SIMFUEL systems, the damage to ceramics imparted by high-energy FPs is often mimicked via heavy ion bombardment (using e.g., Xe) in a particle accelerator, with kinetic energies approaching that observed in fission (~170 MeV) [40]. These short-ranged (order of µm) interactions from heavy ions cause lattice dislocations and ionisation along the path of travel, imparting significant heat to the ceramic; α particles behave in a similar manner though with a longer range as the mass is far lighter and velocity higher than other FP ions [40]. The deceleration of β particles within ceramics (range order of cm) results in ionisation along the path of travel and the generation of bremsstrahlung X-rays; β irradiations can be conducted using specialised electron guns [43].…”

mentioning

confidence: 99%

The Effects of Irradiation on Structure and Leaching of Pure and Doped Thin-Film Ceria SIMFUEL Models Prepared via Polymer-Templated Deposition

Holdsworth,

Feng,

Edge

et al. 2024

JNE

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When studying hazardous materials such as spent nuclear fuel (SNF), the minimisation of sample volumes is essential, together with the use of chemically-similar surrogates where possible. For example, the bulk behaviour of urania (UO2) can be mimicked by appropriately-engineered thin films of sufficient thickness, and inactive materials such as ceria (CeO2) can be used to study the effects within radioactive systems used to fuel nuclear fission. However, thin film properties are sensitive to the preparative method, many of which require the use of highly toxic precursors and specialised apparatus (e.g., chemical vapour deposition). To address this, we present the development of a flexible, tuneable, scalable method for the preparation of thin-film CeO2 SIMFUEL models with a thickness of ≈5 μm. The effects of γ irradiation (up to 100 kGy) and dopants including trivalent lanthanides (Ln3+) and simulant ε-particles on the structure and long-term leaching of these systems under SNF storage conditions were explored, alongside the context of this within further work. It was found that the sensitivity of CeO2 films to reduction upon irradiation, particularly in the presence of simulant ε-particles, resulted in increased leaching of Ce (as CeIII), while trivalent lanthanides (Nd3+ and Eu3+) had a minimal effect on Ce leaching.

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An attempt to reproduce high burn-up structure by ion irradiation of SIMFUEL

Cited by 13 publications

References 23 publications

Thermal Energy Transport in Oxide Nuclear Fuel

Thermal Energy Transport in Oxide Nuclear Fuel

On Morphological and Microstructural Changes in Uranium Dioxide Powder during Binder-Free Hot Pressing

The Effects of Irradiation on Structure and Leaching of Pure and Doped Thin-Film Ceria SIMFUEL Models Prepared via Polymer-Templated Deposition

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