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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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  • Recent advances in the development of the finite-element based, multidimensional fuel performance code BISON of Idaho National Laboratory are presented. Specifically, the development, implementation and testing of a new model for the analysis of fission gas behavior in LWR-UO2 fuel during irradiation are summarized. While retaining a physics-based description of the relevant mechanisms, the model is characterized by a level of complexity suitable for application to engineering-scale nuclear fuel analysis and consistent with the uncertainties pertaining to some parameters. The treatment includes the fundamental features of fission gas behavior, among which are gas diffusion and precipitation in fuel grains, growthmore » and coalescence of gas bubbles at grain faces, grain growth and grain boundary sweeping effects, thermal, athermal, and transient gas release. The BISON code incorporating the new model is applied to the simulation of irradiation experiments from the OECD/NEA International Fuel Performance Experiments database, also included in the IAEA coordinated research projects FUMEX-II and FUMEX-III. The comparison of the results with the available experimental data at moderate burn-up is presented, pointing out an encouraging predictive accuracy, without any fitting applied to the model parameters.« less
  • A model employing Darcy's law has been developed to describe the transient pressure field within interconnected porosity of mixed-oxide liquid-metal fast breeder reactor fuel during hypothetical reactor accidents. Pressure increases are due both to fission gas released from fuel grains and fill gas originally present within fuel pores. Calculations utilizing the model have been performed for an out-of-pile test prior to fuel melting with both clad and unclad conditions being treated. Redistribution of gas from the source region in the relatively high-porosity unrestructured fuel to a low-porosity restructured fuel was shown to exist in all cases considered. Even for themore » unclad case, significant internal pressurization was predicted by the model, which could prove important in subsequent fuel breakup and motion.« less
  • A fission gas code, GRABB, is developed to model intragranular and grain boundary fission gas development and release in a fast thermal transient. Transient direct electrical heating fission gas data, test 33, is simulated with GRABB and GRASS-SST. The computations show that accurate fuel modeling requires consideration of grain edge fission gas and a grain surface bubble interlinkage mechanism. Swelling data are slightly better predicted by GRABB than by GRASS-SST. Both codes underestimate the low temperature gas release data. The GRAS-SSST code underestimates the intermediate temperature gas release while GRABB predictions are within the scatter of the data. The highmore » temperature gas release is overestimated by GRASS-SST while GRABB underestimates it.« less