Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments
Source abstract
Abstract
Abstract In a light water nuclear reactor environment, zirconium-alloy cladding undergoes corrosion that introduces hydrogen into the cladding. Hydrogen being slightly soluble in zirconium means that the terminal solid solubility of hydrogen is quickly reached. This leads to hydrogen precipitation into crystals of zirconium hydride. These hydrides decrease the ductility of the cladding, which increases the chance of cladding failure, especially during dry storage or transportation events, depending on the temperature and stress conditions. In this work, we tested the existing hydrogen migration and redistribution model implemented in the Bison fuel performance code by comparing Bison predictions of hydrogen distribution in various temperature profiles against historical published experimental data. Using 1D simulations of hydrogen evolution in zirconium-alloy, we demonstrated the accuracy of the existing model in the case of a sharp temperature gradient profile. We also performed a sensitivity analysis to investigate the impact of the model parameters on Bison predictions of hydrogen migration and redistribution to understand the discrepancies in the case of a low temperature gradient profile. In both cases, the Bison prediction of hydrogen distribution is accurate in the regions where the temperatures are higher. In these areas, the relative error on average does not exceed 1%. On the other hand, the error grows increasingly higher in the cold regions where hydrides are more likely to form and a steep gradient in the hydrogen concentration profile develops. The potential for the uncertainties in the model parameters to explain this behavior is investigated through the sensitivity analysis, including the impact of a clamping factor that artificially reduces the maximum allowable volume fraction of hydrides. This study also provides a literature review on hydrogen migration and redistribution experiments and a systematic comparison of the relative experimental data.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (29)
Show source-provided references
1. Hydride formation in zirconium alloys10.1007/s11837-012-0479-x ↗
2. Zirconium hydrides and their effect on the circumferential mechanical properties of Zr-Sn-Fe-Nb tubes10.1016/S0925-8388(02)00527-3 ↗
3. Multidimensional simulations of hydrides during fuel rod lifecycle10.1016/j.jnucmat.2015.06.037 ↗
4. Modeling and simulation of hydrogen behavior in zircaloy-4 fuel cladding10.1016/j.jnucmat.2014.05.013 ↗
5. Hydrogen pickup and redistribution in alpha-annealed zircaloy-4
6. Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, zircaloy-2 and zircaloy-410.1016/0022-3115(67)90047-5 ↗
7. The diffusion and solubility of hydrogen in the alpha phase of zircaloy-210.1016/0022-3115(60)90025-8 ↗
8. The terminal solid solubility of hydrogen in zirconium alloys
9. Marino · 1974
10. Review of the thermodynamic basis for models of delayed hydride cracking rate in zirconium alloys10.1016/j.jnucmat.2009.06.022 ↗
11. Diffusion coefficient of hydrogen in alpha zirconium, zircaloy-2 and zircaloy-410.1016/0022-3115(72)90065-7 ↗
12. Solubility and diffusion of hydrogen in zirconium
13. The heat of transport of hydrogen in zirconium alloys10.1016/0022-3115(63)90154-5 ↗
14. Schwartz · Trans. Amer. Soc. Metals · 1954 · 46 · 640
15. Gulbransen · Trans. AIME · 1955 · 203 · 136
16. Mallett · J. Electro- Them. Sot. · 1957 · 104 · 14210.1149/1.2428522 ↗
17. The zirconium-hydrogen system: some thermodynamic properties from a heat content study10.1021/ja01552a010 ↗
18. Dissolution and precipitation behavior of hydrides in zircaloy-2 and high fe zircaloy10.1016/S0022-3115(03)00320-9 ↗
19. Terminal solid solubility of hydrogen in unalloyed zirconium by differential scanning calorimetry10.1080/18811248.2004.9715569 ↗
20. Dissolution and precipitation behaviors of hydrides in n18, zry-4 and m5 alloys10.1016/j.ijhydene.2009.07.018 ↗
21. Synchrotron diffraction study of dissolution and precipitation kinetics of hydrides in zircaloy-410.1016/j.jnucmat.2011.11.009 ↗
22. Colas · 2012
23. The terminal solid solubility of hydrogen in irradiated zircaloy-2 and microscopic modeling of hydride behavior10.1016/j.jnucmat.2009.01.017 ↗
24. Multidimensional multiphysics simulation of nuclear fuel behavior10.1016/j.jnucmat.2012.01.012 ↗
25. Adams · 2011
26. Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron radiation diffraction10.1016/j.jnucmat.2009.04.004 ↗
27. Hydride precipitation kinetics in Zircaloy-4 studied using synchrotron X-ray diffraction10.1016/j.jnucmat.2015.02.035 ↗
28. George · 2003
29. Variance-based sensitivity analysis applied to the hydrogen migration and redistribution model in Bison. Part II: Uncertainty quantification and optimization10.1016/j.jnucmat.2019.06.023 ↗