journal article·2022-01

Systematic sensitivity analysis of Ag release from TRISO particle during AGR-1 irradiation test and high temperature annealing safety test

Seok Bin Seo, Nicholas R. Brown, Giovanni Pastore, Brian D. Wirth

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Abstract

Abstract This paper describes the results of a systematic sensitivity analysis for silver diffusional release from Tristructural Isotropic (TRISO) fuel particles in the AGR-1 base irradiation test and high temperature safety test database. The BISON code was used to model the diffusional release of silver through the coated particle for a wide range of the irradiation and the high temperature conditions conducted in the AGR-1 tests. The current BISON results agree well with other computations and measurements. We then conducted the systematic sensitivity analysis to identify the impact of Ag diffusion coefficient in the TRISO layer materials on the prediction of Ag release. Sobol indices were computed to indicate the contribution of each input, and the scatter plots were analyzed to investigate the correlations between diffusivity parameters and predicted Ag release. Informed by the Sobol sensitivity analysis, a calibrated set of diffusion coefficients were obtained which gave better predictions. The result of this best-estimate calibration indicates a Ag diffusion pre-factor in the SiC from 3.85 × 10−10 to 3.19 × 10−9 m2/s and Ag activation energy in SiC between 178 and 185 kJ/mole. The outputs are expected to provide the systematic approach for better understanding of Ag transport inside TRISO particle.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Graphite, nuclear technology, radiation studies

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References (39)

Show source-provided references
1. A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications10.1016/j.jnucmat.2020.152139 ↗
2. Review of progress in coated fuel particle performance analysis10.1080/00295639.2019.1686882 ↗
3. Investigation of the impurities and fission products in the AVR coolant gas at an average hot-gas temperature of 950°C10.1016/0029-5493(75)90158-2 ↗
4. Silver release from coated particle fuel10.13182/NT35-483 ↗
5. Release behavior of metallic fission products from HTGR fuel particles at 1600 to 1900°C10.1016/0022-3115(93)90027-V ↗
6. Distribution of fission products palladium, silver, cerium and cesium in the un-corroded areas of the locally corroded SiC layer of a neutron irradiated TRISO fuel particle10.1016/j.jeurceramsoc.2017.04.012 ↗
7. Silver (Ag) transport mechanisms in TRISO coated particles: a critical review10.1016/j.nucengdes.2013.11.029 ↗
8. Preliminary results of post-irradiation examination of the AGR-1 TRISO fuel compacts
9. Irradiation performance of AGR-1 high temperature reactor fuel10.1016/j.nucengdes.2015.09.011 ↗
10. Considerations pertaining to the achievement of high burn-ups in HTR fuel10.1016/S0029-5493(01)00502-7 ↗
11. The ATLAS HTR fuel simulation code objectives, description and first results
12. Development of an integrated fission product release and transport code for spatially resolved full-core calculations of V/HTRs10.1016/j.nucengdes.2013.11.063 ↗
13. Wang · 2004
14. Boer · 2009
15. van der Merwe · 2009
16. Verification of fission product release model from high temperature engineering test reactor fuel10.1080/18811248.1992.9731603 ↗
17. Comparison of silver, cesium, and strontium release predictions using PARFUME with results from the AGR-1 irradiation experiment10.1016/j.jnucmat.2015.08.033 ↗
18. Multidimensional multiphysics simulation of TRISO particle fuel10.1016/j.jnucmat.2013.07.070 ↗
19. TRISO particle fuel performance and failure analysis with BISON10.1016/j.jnucmat.2021.152795 ↗
20. Modeling fission product diffusion in TRISO fuel particles with BISON10.1016/j.jnucmat.2021.152840 ↗
21. A review of TRISO fuel performance models10.1016/j.jnucmat.2010.07.030 ↗
22. Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests10.1016/j.nucengdes.2019.110428 ↗
23. Demkowicz · 2015
24. Completion of the first NGNP advanced gas reactor fuel irradiation experiment, AGR-1, in the advanced test reactor
25. Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests10.1016/j.nucengdes.2016.03.023 ↗
26. Multidimensional multiphysics simulation of nuclear fuel behavior10.1016/j.jnucmat.2012.01.012 ↗
27. Sensitivity estimates for non linear mathematical models
28. Variance based sensitivity analysis of model output. Design and estimator for the total sensitivity index10.1016/j.cpc.2009.09.018 ↗
29. Making best use of model evaluations to compute sensitivity indices10.1016/S0010-4655(02)00280-1 ↗
30. Global sensitivity analysis of environmental models: convergence and validation10.1016/j.envsoft.2016.02.005 ↗
31. SALib: an open-source Python library for sensitivity analysis
32. Fuel performance and fission product behavior in gas cooled reactors
33. Diffusion of silver and cesium in silicon-carbide coatings of fuel particles for high-temperature gas-cooled reactors10.13182/NT61-475 ↗
34. Chernikov · 1986
35. Verfondern · 1993
36. Fukuda · 1989
37. Investigation of silver and iodine transport through silicon carbide layers prepared for nuclear fuel element cladding10.1016/j.jnucmat.2010.12.243 ↗
38. First high temperature safety tests of AGR-1 TRISO fuel with the fuel accident condition simulator (FACS) furnace10.1016/j.jnucmat.2015.05.006 ↗
39. Hunn · 2015