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Title: Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS

Abstract

The modelling of fission gas behaviour is a crucial aspect of nuclear fuel analysis in view of the related effects on the thermo-mechanical performance of the fuel rod, which can be particularly significant during transients. Experimental observations indicate that substantial fission gas release (FGR) can occur on a small time scale during transients (burst release). To accurately reproduce the rapid kinetics of burst release in fuel performance calculations, a model that accounts for non-diffusional mechanisms such as fuel micro-cracking is needed. In this work, we present and assess a model for transient fission gas behaviour in oxide fuel, which is applied as an extension of diffusion-based models to allow for the burst release effect. The concept and governing equations of the model are presented, and the effect of the newly introduced parameters is evaluated through an analytic sensitivity analysis. Then, the model is assessed for application to integral fuel rod analysis. The approach that we take for model assessment involves implementation in two structurally different fuel performance codes, namely, BISON (multi-dimensional finite element code) and TRANSURANUS (1.5D semi-analytic code). The model is validated against 19 Light Water Reactor fuel rod irradiation experiments from the OECD/NEA IFPE (International Fuel Performance Experiments)more » database, all of which are simulated with both codes. The results point out an improvement in both the qualitative representation of the FGR kinetics and the quantitative predictions of integral fuel rod FGR, relative to the canonical, purely diffusion-based models, with both codes. The overall quantitative improvement of the FGR predictions in the two codes is comparable. Furthermore, calculated radial profiles of xenon concentration are investigated and compared to experimental data, demonstrating the representation of the underlying mechanisms of burst release by the new model.« less

Authors:
ORCiD logo [1];  [1];  [1];  [2];  [3];  [2];  [1]
  1. Politecnico di Milano, Milano (Italy)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. European Commission, Karlsruhe (Germany)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1372265
Report Number(s):
INL/JOU-16-39206
Journal ID: ISSN 0022-3115; PII: S002231151630544X
Grant/Contract Number:  
AC07-05ID14517
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 486; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BISON code; Fission gas behavior; Nuclear fuel modeling; Fission gas; Burst release; Fuel modelling; TRANSURANUS code

Citation Formats

Barani, T., Bruschi, E., Pizzocri, D., Pastore, G., Van Uffelen, P., Williamson, R. L., and Luzzi, Lelio. Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2016.10.051.
Barani, T., Bruschi, E., Pizzocri, D., Pastore, G., Van Uffelen, P., Williamson, R. L., & Luzzi, Lelio. Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS. United States. doi:10.1016/j.jnucmat.2016.10.051.
Barani, T., Bruschi, E., Pizzocri, D., Pastore, G., Van Uffelen, P., Williamson, R. L., and Luzzi, Lelio. Tue . "Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS". United States. doi:10.1016/j.jnucmat.2016.10.051. https://www.osti.gov/servlets/purl/1372265.
@article{osti_1372265,
title = {Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS},
author = {Barani, T. and Bruschi, E. and Pizzocri, D. and Pastore, G. and Van Uffelen, P. and Williamson, R. L. and Luzzi, Lelio},
abstractNote = {The modelling of fission gas behaviour is a crucial aspect of nuclear fuel analysis in view of the related effects on the thermo-mechanical performance of the fuel rod, which can be particularly significant during transients. Experimental observations indicate that substantial fission gas release (FGR) can occur on a small time scale during transients (burst release). To accurately reproduce the rapid kinetics of burst release in fuel performance calculations, a model that accounts for non-diffusional mechanisms such as fuel micro-cracking is needed. In this work, we present and assess a model for transient fission gas behaviour in oxide fuel, which is applied as an extension of diffusion-based models to allow for the burst release effect. The concept and governing equations of the model are presented, and the effect of the newly introduced parameters is evaluated through an analytic sensitivity analysis. Then, the model is assessed for application to integral fuel rod analysis. The approach that we take for model assessment involves implementation in two structurally different fuel performance codes, namely, BISON (multi-dimensional finite element code) and TRANSURANUS (1.5D semi-analytic code). The model is validated against 19 Light Water Reactor fuel rod irradiation experiments from the OECD/NEA IFPE (International Fuel Performance Experiments) database, all of which are simulated with both codes. The results point out an improvement in both the qualitative representation of the FGR kinetics and the quantitative predictions of integral fuel rod FGR, relative to the canonical, purely diffusion-based models, with both codes. The overall quantitative improvement of the FGR predictions in the two codes is comparable. Furthermore, calculated radial profiles of xenon concentration are investigated and compared to experimental data, demonstrating the representation of the underlying mechanisms of burst release by the new model.},
doi = {10.1016/j.jnucmat.2016.10.051},
journal = {Journal of Nuclear Materials},
number = C,
volume = 486,
place = {United States},
year = {Tue Jan 03 00:00:00 EST 2017},
month = {Tue Jan 03 00:00:00 EST 2017}
}

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