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Title: A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

Journal Article · · Journal of Nuclear Materials

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
Citation Metrics:
Cited by: 28 works
Citation information provided by
Web of Science

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