Metal fission product behaviour in high temperature reactors -UO2 coated particle fuel

Brown, P. E.; Faircloth, R.L.

doi:10.1016/0022-3115(76)90005-2

Cited by 62 publications

(30 citation statements)

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“…Using the analytical solution for release from a thin spherical shell, the "diffusion" coefficient necessary to produce that silver release can be calculated for each heat treatment as follows (Crank 1956). The effective mass transport coefficients calculated from the mass loss data for the current silver experiment are plotted along with the diffusion coefficients reported in the literature in Figure 3-2 (Nabielek, Brown, and Offerman 1977, Brown and Faircloth 1976, Förthmann et al 1982, Amian and Stöver 1983. The calculated diffusion coefficients from the complete set of experiments continue to appear higher than the literature band, but there is overlap between the data sets.…”

Section: Mass Lossmentioning

confidence: 77%

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels (I-NERI Annual Report)

Petti¹,

Maki²,

Languille³

et al. 2002

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The objective of this INERI project is to develop improved fuel behavior models for gas reactor coated particle fuels and to develop improved coated-particle fuel designs that can be used reliably at very high burnups and potentially in fast gas-cooled reactors. Thermomechanical, thermophysical, and physiochemical material properties data were compiled by both the US and the French and preliminary assessments conducted. Comparison between U.S. and European data revealed many similarities and a few important differences. In all cases, the data needed for accurate fuel performance modeling of coated particle fuel at high burnup were lacking. The development of the INEEL fuel performance model, PARFUME, continued from earlier efforts.The statistical model being used to simulate the detailed finite element calculations is being upgraded and improved to allow for changes in fuel design attributes (e.g. thickness of layers, dimensions of kernel) as well as changes in important material properties to increase the flexibility of the code. In addition, modeling of other potentially important failure modes such as debonding and asphericity was started. A paper on the status of the model was presented at the HTR-2002 meeting in Petten, Netherlands in April 2002, and a paper on the statistical method was submitted to the Journal of Nuclear Material in September 2002. Benchmarking of the model against Japanese and an older DRAGON irradiation are planned. Preliminary calculations of the stresses in a coated particle have been calculated by the CEA using the ATLAS finite element model. This model and the material properties and constitutive relationships will be incorporated into a more general software platform termed Pleiades. Pleiades will be able to analyze different fuel forms at different scales (from particle to fuel body) and also handle the statistical variability in coated particle fuel. Diffusion couple experiments to study Ag and Pd transport through SiC were conducted. Analysis and characterization of the samples continues. Two active transport mechanisms are proposed: diffusion in SiC and release through SiC cracks or another, as yet undetermined, path. Silver concentration profiles determined by XPS analysis suggest diffusion within the SiC layer, most likely dominated by grain boundary diffusion. However, diffusion coefficients calculated from mass loss measurements suggest a much faster release path, postulated as small cracks or flaws that provide open paths with little resistance to silver migration. Work is ongoing to identify and characterize this path. Work on Pd behavior has begun and will continue next year. INTRODUCTIONThe objectives of this INERI project are to:develop improved fuel behavior models for gas cooled reactor particle fuels (initially for TRISO-coated fuels), develop improved gas cooled reactor particle fuel coating materials and designs that will reliably reach very high burnups, assess the extension of the particle fuel concept to hard spectrum gas-cooled cores, and develop an irradiati...

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Section: Mass Lossmentioning

confidence: 77%

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels (I-NERI Annual Report)

Petti¹,

Maki²,

Languille³

et al. 2002

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“…Amorphous SiC (a-SiC) structure Open symbols are measurement from irradiated TRISO particles and filled symbols represents reported values from non-irradiated SiC from both surrogate experimental and computational studies. Ref 7,[75][76][77][78][79][80] are integral release data from irradiated TRISO particles. Ref 13,14 are the upper bounds for D for Cs in crystalline 3C-SiC and ∑5-GB from computational study.…”

Section: Appendixesmentioning

confidence: 99%

Cs diffusion in SiC high-energy grain boundaries

Szlufarska

Morgan

2017

Journal of Applied Physics

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Cesium (Cs) is a radioactive fission product whose release is of concern for Tristructural-Isotropic (TRISO) fuel particles. In this work, Cs diffusion through high energy grain boundaries (HEGBs) of cubic-SiC is studied using an ab-initio based kinetic Monte Carlo (kMC) model. The HEGB environment was modeled as an amorphous SiC (a-SiC), and Cs defect energies were calculated using density functional theory (DFT). From defect energies, it was suggested that the fastest diffusion mechanism as Cs interstitial in an amorphous SiC. The diffusion of Cs interstitial was simulated using a kMC, based on the site and transition state energies sampled from the DFT. The Cs HEGB diffusion exhibited an Arrhenius type diffusion in the range of 1200-1600°C. The comparison between HEGB results and the other studies suggests not only that the GB diffusion dominates the bulk diffusion, but also that the HEGB is one of the fastest grain boundary paths for the Cs diffusion. The diffusion coefficients in HEGB are clearly a few orders of magnitude lower than the reported diffusion coefficients from in-and out-of-pile samples, suggesting that other contributions are responsible, such as a radiation enhanced diffusion.

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“…three coatings). The partition factor γ i , is introduced to allow for discontinuous concentrations at the interface [Dunlap and Gulden, 1968;Brown and Faircloth, 1976]. An analytical eigenfunction expansion approach for solving similar multilayer problems in heat conduction has been reported [Mulholland and Cobble, 1972;Ozisik, 1980].…”

Section: Exact Multilayer Modelmentioning

confidence: 99%

“…An advantage of the Booth model is that the release fraction is a simple analytical expression, thus eliminating extensive computations. However, for multicoated fuels, only numerical solutions [Brown and Faircloth, 1976;Kurata, 1981;Amian and Stover, 1982], or semi-analytic approximations [Smith et al, 1977] have been documented in the literature. In all these cases, significant computational resources are required and the results are limited by discretization or approximation errors.…”

Section: Introductionmentioning

confidence: 99%

Analytical Modeling of Fission Product Releases by Diffusion from Multicoated Fuel Particles

Gelbard¹

2003

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Three levels of fission product diffusional release models are solved exactly. First, the Booth model for a homogenous uncoated spherical fuel particle is presented and an improved implementation is suggested. Second, the release from a fuel particle with a single barrier layer is derived as a simple alternative to account for a coating layer. Third, the general case of release from a multicoated fuel particle is derived and applied to a TRISO-coated fuel. Previous approaches required approximate numerical solutions for the case of an arbitrary number of coatings with arbitrary diffusivities and arbitrary coating interface conditions.

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Metal fission product behaviour in high temperature reactors -UO2 coated particle fuel

Cited by 62 publications

References 0 publications

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels (I-NERI Annual Report)

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels (I-NERI Annual Report)

Cs diffusion in SiC high-energy grain boundaries

Analytical Modeling of Fission Product Releases by Diffusion from Multicoated Fuel Particles

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