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http://dx.doi.org/10.1016/j.net.2022.06.025

Development and validation of FRAT code for coated particle fuel failure analysis  

Jian Li (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University)
Ding She (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University)
Lei Shi (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University)
Jun Sun (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University)
Publication Information
Nuclear Engineering and Technology / v.54, no.11, 2022 , pp. 4049-4061 More about this Journal
Abstract
TRISO-coated particle fuel is widely used in high temperature gas cooled reactors and other advanced reactors. The performance of coated fuel particle is one of the fundamental bases of reactor safety. The failure probability of coated fuel particle should be evaluated and determined through suitable fuel performance models and methods during normal and accident condition. In order to better facilitate the design of coated particle fuel, a new TRISO fuel performance code named FRAT (Fission product Release Analysis Tool) was developed. FRAT is designed to calculate internal gas pressure, mechanical stress and failure probability of a coated fuel particle. In this paper, FRAT was introduced and benchmarked against IAEA CRP-6 benchmark cases for coated particle failure analysis. FRAT's results agree well with benchmark values, showing the correctness and satisfactory applicability. This work helps to provide a foundation for the credible application of FRAT.
Keywords
TRISO-coated fuel particlc; Fuel performance; FRAT; IAEA CRP-6 benchmark; Code validation;
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  • Reference
1 Z.X. Wu, Z.Y. Zhang, The Advanced Nuclear Energy System and High Temperature Gas-Cooled Reactor, Tsinghua University Press, 2004 in Chinese.
2 J.J. Powers, et al., A review of TRISO fuel performance models, J. Nucl. Mater. 405 (2010) 74-82.   DOI
3 K. Verfondern, et al., PANAMA e Ein Rechenprogramm zur Vorhersage des partikelbruchanteils von TRISO-partikeln unter Storfallbedingungen, 1985. FZJ report Jul-Spez-298.
4 M. Phelip, et al., The ATLAS HTR fuel simulation code objectives, description and first results, in: The 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22-26, 2004.
5 I. Golubev, et al., Development of the code GOLT for performance evaluation of coated particles fuel, in: The 4th International Topical Meeting on High Temperature Reactor Technology, Washington, DC, USA, September 28-October 1, 2008.
6 K. Sawa, et al., Development of a coated fuel particle failure model under high burnup irradiation, J. Nucl. Sci. Technol. 33 (1996) 712.
7 D. Pelessone, et al., PISA: a one-dimensional spherically symmetric computer program to perform thermal and stress analysis of irradiated fuel particles, General Atomics (1992). CEGA-M-92-2052.
8 J.S. Bradley, et al., Software design description and user's manual for CAPPER irradiation capsule performance computer code, General Atomics (1992). CEGA-002309.
9 D.G. Martin, Considerations pertaining to the achievement of high burn-ups in HTR fuel, Nucl. Eng. Des. 213 (2002) 241-258.   DOI
10 M.K. Young, et al., Development of a fuel performance analysis code COPA, in: Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, Washington, DC USA, 2008.
11 G.K. Miller, et al., PARFUME Theory and Model Basis Report, Idaho National Laboratory, 2009. INL/EXT-08-14497.
12 R.L. Williamson, et al., Overview of the BISON Multidimensional Fuel Performance Code, Idaho National Laboratory, 2013. INL/CON-13-29588.
13 Z.Y. Zhang, et al., Current status and technical description of Chinese 2×250 MWth HTR-PM demonstration plant, Nucl. Eng. Des. 239 (2009) 1212-1219.   DOI
14 D. She, B. Xia, J. Guo, et al., Prediction calculations for the first criticality of the HTR-PM using the PANGU code, Nucl. Sci. Tech. 32 (9) (2021) 1-7.   DOI
15 D. She, J. Guo, Z. Liu, et al., PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations, Ann. Nucl. Energy 126 (2018) 48-58.
16 J. Li, D. She, L. Shi, The NUIT code for nuclide inventory calculations, Ann. Nucl. Energy 148 (11) (2020), 107690.
17 D. Zudkevitch, et al., Correlation and prediction of vapor-liquid equilibria with the Redlich-Kwong equation of state, AIChE J. 16 (1) (1970) 112-119.   DOI
18 G.K. Miller, et al., Updated solution for stresses and displacements in TRISOcoated fuel particles, J. Nucl. Mater. 374 (2008) 129-137.   DOI
19 E. Proksch, et al., Production of carbon monoxide during burnup of UO2 kerneled HTR fuel particles, J. Nucl. Mater. 107 (1982) 280-285.   DOI
20 IAEA, Advances in High Temperature Gas Cooled Reactor Fuel Technology, 2012. IAEA-TECDOC-CD-1674.