On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation
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Besides recent progresses in the physics-based modelling of fission gas and helium behaviour, thescarcity of experimental data concerning their combined behaviour (i.e., cocktail) hinders further modeldevelopments. For this reason, in this work, we propose a modelling methodology aimed at providingrecommendations for accelerated experimental investigations. By exploring a wide range of annealingtemperatures and cocktail compositions with a physics-based modelling approach we identify the mostinteresting conditions to be targeted by future experiments. To corroborate the recommendations arisingfrom the proposed methodology, we include a sensitivity analysis quantifying the impact of the modelparameters on fission gas and helium release, in conditions representative of high and low burnup
Abstract
Besides recent progresses in the physics-based modelling of fission gas and helium behaviour, thescarcity of experimental data concerning their combined behaviour (i.e., cocktail) hinders further modeldevelopments. For this reason, in this work, we propose a modelling methodology aimed at providingrecommendations for accelerated experimental investigations. By exploring a wide range of annealingtemperatures and cocktail compositions with a physics-based modelling approach we identify the mostinteresting conditions to be targeted by future experiments. To corroborate the recommendations arisingfrom the proposed methodology, we include a sensitivity analysis quantifying the impact of the modelparameters on fission gas and helium release, in conditions representative of high and low burnup
참고문헌 (34)
- A. T. Motta, "Light Water Reactor Materials,vol. I, Fundamentals" (2017), American Nuclear Society Scientific Publications
- Hj. Matzke, "Gas release mechanisms in UO2-a critical review", Radiat. Eff, 53, pp.219~242 (1980)[DOI]
- J. Rest, "Fission gas release from UO2 nuclear fuel : a review", J. Nucl. Mater, 513, pp.310~345 (2019)
- P. Van Uffelen, "A review of fuel performance modelling", J. Nucl. Mater, 516, pp.373~412 (2019)[DOI]
- P. Botazzoli, "Helium Production and Behaviour in LWR Oxide Nuclear Fuels", PhD, pp.2011
- G. Pastore, "Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis", Nucl. Eng. Des, 256, pp.75~86 (2013)[DOI]
- L. Cognini, "Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes", Nuclear Engineering and Technology, 53(2), pp.562~571 (2021), 한국원자력학회[DOI]
- D. Pizzocri, "A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools", J. Nucl. Mater, 502, pp.323~330 (2018)[DOI]
- J. Rest, "FASTGRASS : A Mechanistic Model for the Prediction of Xe, I, Cs, Te, Ba, and Sr Release from Nuclear Fuel under Normal and Severe-Accident Conditions", ~
- M. S. Veshchunov, "Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel", Nucl. Eng. Des, 236, pp.179~200 (2006)[DOI]
- L. Noirot, "MARGARET : a comprehensive code for the description of fission gas behavior", Nucl. Eng. Des, 241, pp.2099~2118 (2011)[DOI]
- G. Jomard, "CARACAS :an industrial model for the description of fission gas behavior in LWR-UO2fuel", World React. Fuel Perform. Meet., Sendai, pp.14~17 (2014)
- I. Zacharie, "Thermal treatment of uranium oxide irradiated in pressurized water reactor : swelling and release of fission gases", J. Nucl. Mater, 255, pp.85~91 (1998)[DOI]
- R. J. White, "The development of grain-face porosity in irradiated oxide fuel", J. Nucl. Mater, 325, pp.61~77 (2004)[DOI]
- S. Kashibe, "Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6-83 GWd", t, 1993, pp.206, 22~34
- E. Maugeri, "Helium solubility and behaviour in uranium dioxide", J. Nucl. Mater, 385, pp.461~466 (2009)[DOI]
- Z. Talip, "Helium behaviour in stoichiometric and hyperstoichiometric UO2", J. Eur. Ceram. Soc, 34, pp.1265~1277 (2014)[DOI]
- Z. Talip, "Thermal diffusion of helium in 238Pu-doped UO2", J. Nucl. Mater, 445, pp.117~127 (2014)[DOI]
- G. Martin, "Helium release in uranium dioxide in relation to grain boundaries and free surfaces", Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. Atoms, 268, pp.2133~2137 (2010)[DOI]
- J. -P. Hiernaut, "Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen", J. Nucl. Mater, 377, pp.313~324 (2008)[DOI]
- J. P. Hiernaut, "Specific low temperature release of 131Xe from irradiated MOX fuel", J. Nucl. Mater, 392, pp.434~438 (2009)[DOI]
- D. Pizzocri, "A model describing intra-granular fission gas behaviour in oxide fuel", J. Nucl. Mater, 502, pp.323~330 (2018)
- D. Pizzocri, "SCIANTIX : a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes", J. Nucl. Mater, 532, pp.152042~ (2020)
- "SCIANTIX code, Online Repos"[URL]
- D. R. Olander, "Re-solution of fission gas-a review : Part I. Intragranular bubbles", J. Nucl. Mater, 354, pp.94~109 (2006)[DOI]
- P. Sung, "Equilibrium Solubility and Diffusivity of Helium in Single-Crystal Uranium Dioxide", PhD, pp.1967
- L. Cognini, "Helium solubility in oxide nuclear fuel : derivation of new correlations for Henry's constant", Nucl. Eng. Des, 340, pp.240~244 (2018)[DOI]
- H. Liu, "Carnahan-Starling type equations of state for stable hard disk and hard sphere fluids", Mol. Phys, 119, pp.1905897~ (2021)
- L. Van Brutzel, "A new equation of state for helium nanobubbles embedded in UO2 matrix calculated via molucelar dynamics simulations", J. Nucl. Mater, 518, pp.431~439 (2019)
- T. Kogai, "Modelling of fission gas release and gaseous swelling of light water reactor fuels", J. Nucl. Mater, 244, pp.131~140 (1997)[DOI]
- L. Luzzi, "Helium diffusivity in oxide nuclear fuel : critical data analysis and new correlations", Nucl. Eng. Des, 330, pp.265~271 (2018)[DOI]
- J. Turnbull, "The diffusion coefficient for fission gas atoms in uranium dioxide", Proc. A Tech. Comm. Meet. Organ. by Int, pp.18~22 (1989), Energy Agency Held Preston
- G. Pastore, "Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling", J. Nucl. Mater, 456, pp.398~408 (2015)[DOI]
- F. S. Ham, "Theory of diffusion-limited precipitation", J. Phys. Chem. Solid, 6, pp.335~351 (1958)
