Acknowledgement
This work is supported by the China National Key R&D Program (2020YFE0202500), China National S&T Major Project (Grant No. ZX06901/ZX06902), China Postdoctoral Science Foundation (Grant No. 2021M691745), and Young Talent Project of China National Nuclear Corporation (CNNC).
References
- Z.X. Wu, Z.Y. Zhang, The Advanced Nuclear Energy System and High Temperature Gas-Cooled Reactor, Tsinghua University Press, 2004 in Chinese.
- J.J. Powers, et al., A review of TRISO fuel performance models, J. Nucl. Mater. 405 (2010) 74-82. https://doi.org/10.1016/j.jnucmat.2010.07.030
- K. Verfondern, et al., PANAMA e Ein Rechenprogramm zur Vorhersage des partikelbruchanteils von TRISO-partikeln unter Storfallbedingungen, 1985. FZJ report Jul-Spez-298.
- 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.
- G.K. Miller, et al., PARFUME Theory and Model Basis Report, Idaho National Laboratory, 2009. INL/EXT-08-14497.
- R.L. Williamson, et al., Overview of the BISON Multidimensional Fuel Performance Code, Idaho National Laboratory, 2013. INL/CON-13-29588.
- 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. https://doi.org/10.1016/j.nucengdes.2009.02.023
- 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. https://doi.org/10.1007/s41365-020-00836-0
- 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.
- J. Li, D. She, L. Shi, The NUIT code for nuclide inventory calculations, Ann. Nucl. Energy 148 (11) (2020), 107690.
- 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. https://doi.org/10.1002/aic.690160122
- G.K. Miller, et al., Updated solution for stresses and displacements in TRISOcoated fuel particles, J. Nucl. Mater. 374 (2008) 129-137. https://doi.org/10.1016/j.jnucmat.2007.07.016
- E. Proksch, et al., Production of carbon monoxide during burnup of UO2 kerneled HTR fuel particles, J. Nucl. Mater. 107 (1982) 280-285. https://doi.org/10.1016/0022-3115(82)90426-3
- IAEA, Advances in High Temperature Gas Cooled Reactor Fuel Technology, 2012. IAEA-TECDOC-CD-1674.
- 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.
- 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.
- K. Sawa, et al., Development of a coated fuel particle failure model under high burnup irradiation, J. Nucl. Sci. Technol. 33 (1996) 712.
- 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.
- J.S. Bradley, et al., Software design description and user's manual for CAPPER irradiation capsule performance computer code, General Atomics (1992). CEGA-002309.
- D.G. Martin, Considerations pertaining to the achievement of high burn-ups in HTR fuel, Nucl. Eng. Des. 213 (2002) 241-258. https://doi.org/10.1016/S0029-5493(01)00502-7