A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools
The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear fuel. In this work, we present a model representing the evolution of intra-granular bubbles in terms of bubble number density and average bubble size. The model considers the fundamental processes of single gas atom diffusion, gas bubble nucleation, bubble re-solution, and gas atom trapping at bubbles. The model is derived from a detailed cluster dynamics formulation yet consists of only three differential equations in its final form; hence, it can be efficiently applied in engineering fuel performance codes while retaining a physical basis. We discuss the improvements made in our model in comparison to previous models for intra-granular bubble evolution. We validate the model against experimental data, both in terms of bubble number density and average bubble radius. Lastly, we perform an uncertainty analysis, by propagating the uncertainties in the parameters to the model results.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Energy Efficiency and Renewable Energy (EERE)
- Grant/Contract Number:
- SC0016464; 754329; AC07-05ID14517
- OSTI ID:
- 1421777
- Alternate ID(s):
- OSTI ID: 1631707
- Report Number(s):
- INL/JOU-17-43663-Rev000; S0022311517315039; PII: S0022311517315039
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 502 Journal Issue: C; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- Netherlands
- Language:
- English
Web of Science
Similar Records
M3MS-19IN0101201 Modeling Intra-granular Fission Gas Bubble Evolution in Uranium Dioxide during Transients
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution