Detailed characterisations of high burn-up structures in oxide fuels

Noirot, J.; Desgranges, Lionel; Lamontagne, J.

doi:10.1016/j.jnucmat.2007.04.037

Cited by 150 publications

(79 citation statements)

References 26 publications

(37 reference statements)

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“…This has to be understood with the coming high burnup post irradiation examination results. The relatively low HBS area thicknesses at high burnup might be associated with the steep plutonium increase at the periphery-the plutonium has an effect on HBS formation [5]. Figure 10 shows a SEM image of the 83 GWd/tU sample periphery.…”

Section: Microstructure and Microanalysismentioning

confidence: 99%

HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS

Noirot

Aubrun²,

Desgranges³

et al. 2009

Nuclear Engineering and Technology

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Section: Microstructure and Microanalysismentioning

confidence: 99%

HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS

Noirot

Aubrun²,

Desgranges³

et al. 2009

Nuclear Engineering and Technology

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“…As fission products accumulate within the spot, a portion of them migrate to the surrounding matrix by athermal processes such as recoil and knockout [10][11][12]. The high density of the small pores forms a ring around the spot that becomes visible in the polished fuel cross section [12]. Fig.…”

Section: Microscopic Observationmentioning

confidence: 99%

“…The halos with a diameter of less than 15 µm were mainly observed in the periphery region on the radial cross sections. The halo thickness is on the order of a few fission fragment recoil distances [12]. The halos serve as gas storage sites but most of the fission gases and the solid fission products stay within the spot throughout the fuel life [13].…”

Section: Microscopic Observationmentioning

confidence: 99%

“…According to the review of post irradiation results for OCOM and MIMAS MOX fuel [11], the fission gas bubble size within the Pu spots varies with radial position; the bubbles at the Pu spot in the cooler peripheral region are generally smaller than in the central region where a few large pores with several micron-sized are often observed. In a peripheral Pu spot of MIMAS MOX fuel with an average burnup of 63MWd/kgHM, the bubble sizes ranged between 1µm and 8µm in diameter [12]. In the case of rod 6, some large pores are related to the gas bubbles in the central region.…”

Section: Microscopic Observationmentioning

confidence: 99%

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Ceramography Analysis of Mox Fuel Rods After an Irradiation Test

Kim

Jong²,

Lee³

et al. 2010

Nuclear Engineering and Technology

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“…Furthermore, once Xe atoms start to precipitate to form bubbles, more Xe will precipitate to enlarge the bubble. The exact behavior and details of these events will be dictated by the local temperature, fission rate density, and the local defect density [69].…”

Section: 131mentioning

confidence: 99%

Mesoscale Benchmark Demonstration Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing

Li¹,

Hu²,

Montgomery³

et al. 2012

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SUMMARYA study was conducted to evaluate the capabilities of different numerical methods used to represent microstructure behavior at the mesoscale for irradiated material using an idealized benchmark problem. The purpose of the mesoscale benchmark problem was to provide a common basis for assessing several mesoscale methods to identify the strengths and areas of improvement in the predictive modeling of microstructure evolution. In this work, mesoscale models (phase-field, Potts, and kinetic Monte Carlo) developed by Pacific Northwest National Laboratory, Idaho National Laboratory, Sandia National Laboratory, and Oak Ridge National Laboratory were used to calculate the evolution kinetics of intragranular fission gas bubbles in UO 2 fuel under post-irradiation thermal annealing conditions. The benchmark problem was constructed to include important microstructural evolution kinetics of intragranular fission gas bubble behavior, such as the atomic diffusion of Xe atoms, U vacancies, and O vacancies; the effect of vacancy capture and emission from defects; and the elastic interaction on nonequilibrium gas bubbles. An idealized set of assumptions and a common set of thermodynamic and kinetic data were imposed on the benchmark problem to simplify the mechanisms considered. The modeling capabilities of different methods are compared against selected experimental and simulation results. These comparisons find that while the phase-field methods and Potts kinetic Monte Carlo methods are able to incorporate several of the mechanisms that influence intra-granular bubble growth and coarsening, the Potts model is challenged by the low solubility and long-range diffusion necessary to simulate this problem correctly. The statistical-mechanical nature of Potts kMC requires large ensembles with long simulation times to treat this problem. Future efforts are recommended to construct increasingly more complex mesoscale benchmark problems to further verify and validate the predictive capabilities of the mesoscale modeling methods used in this study.

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Detailed characterisations of high burn-up structures in oxide fuels

Cited by 150 publications

References 26 publications

HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS

HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS

Ceramography Analysis of Mox Fuel Rods After an Irradiation Test

Mesoscale Benchmark Demonstration Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing

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Detailed characterisations of high burn-up structures in oxide fuels

Cited by 150 publications

References 26 publications

HIGH BURNUP CHANGES IN UO2FUELS IRRADIATED UP TO 83 GWD/T IN M5(R)CLADDINGS

HIGH BURNUP CHANGES IN UO2FUELS IRRADIATED UP TO 83 GWD/T IN M5(R)CLADDINGS

Ceramography Analysis of Mox Fuel Rods After an Irradiation Test

Mesoscale Benchmark Demonstration Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing

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HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS

HIGH BURNUP CHANGES IN UO₂FUELS IRRADIATED UP TO 83 GWD/T IN M5^(R)CLADDINGS