Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations

Journal Article · 20 February 2018 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2018.01.044 · OSTI ID:1466656

Luzzi, L. ^[1]; Cognini, L. ^[2]; Pizzocri, D. ^[1]; Barani, T. ^[1]; Pastore, G. ^[3]; Schubert, A. ^[4]; Wiss, T. ^[4]; Van Uffelen, P. ^[4]

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1. Polytechnic Univ. of Milan (Italy). Dept. of Energy. Nuclear Engineering Division
2. Polytechnic Univ. of Milan (Italy). Dept. of Energy. Nuclear Engineering Division; European Commission (EC) Joint Research Centre (JRC), Karlsruhe (Germany). Directorate for Nuclear Safety and Security
3. Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation Dept.
4. European Commission (EC) Joint Research Centre (JRC), Karlsruhe (Germany). Directorate for Nuclear Safety and Security

Helium is relevant in determining nuclear fuel behaviour. It affects the performance of nuclear fuel both in reactor and in storage conditions. Helium becomes important in reactor conditions when high burnups are targeted or MOX fuel is used, whereas for storage conditions it can represent a threat to the fuel rods integrity. The accurate knowledge of helium behaviour combined with predictive model capabilities is fundamental for the safe management of nuclear fuel, with helium diffusivity being a critical property. For this reason, a considerable number of separate effect experiments in the last fifty years investigated helium diffusivity in nuclear fuel. The aim of this work is to critically review and assess the experimental results concerning the helium diffusivity. Experimental results are critically analysed in terms of the helium introduction technique used (either infusion, implantation or doping) and of sample characteristics (single crystal, poly-crystal or powder). Accordingly, we derived two different correlations for the diffusivity. Clearly, each of the new correlations corresponds to a limited range of application conditions, depending on the experimental data used to derive it. We provide recommendations regarding the proper application conditions for each correlation (e.g., in reactor or storage conditions).

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States); Polytechnic Univ. of Milan (Italy); European Commission (EC) Joint Research Centre (JRC), Karlsruhe (Germany)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE); European Commission (EC); European Energy Research Alliance (EERA); International Atomic Energy Agency (IAEA)
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 1466656
• Journal Information: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 330; ISSN 0029-5493
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English