References
- Z. Wu, D. Lin, D. Zhong, The design features of the HTR-10, Nucl. Eng. Des. 218 (2002) 25-32. https://doi.org/10.1016/S0029-5493(02)00182-6
-
Z. Zhang, Z. Wu, D.Wang, Y. Xu, Y. Sun, F. Li, et al., Current status and technical description of Chinese 2
$\times$ 250 MW th HTR-PM demonstration plant, Nucl. Eng. Des. 239 (2009) 1212-1219. https://doi.org/10.1016/j.nucengdes.2009.02.023 - C. Fang, X. Bao, C. Yang, Y. Yang, J. Cao, The R&D of HTGR high temperature helium sampling loop: from HTR-10 to HTR-PM, Nucl. Eng. Des. 306 (2016) 192-197. https://doi.org/10.1016/j.nucengdes.2016.03.012
- A. Dvorzhak, J.C. Mora, B. Robles, C.G. Soares, Probabilistic risk assessment from potential exposures to the public applied for innovative nuclear installations, Reliab. Eng. Syst. Saf. 152 (2016) 176-186. https://doi.org/10.1016/j.ress.2016.03.008
- R. Barati, S. Setayeshi, Functional reliability evaluation of an MTR-pool type research reactor core using the loadecapacity interference model, Ann. Nucl. Energy 58 (2013) 151-160. https://doi.org/10.1016/j.anucene.2013.03.015
- L.P. Pagani, G.E. Apostolakis, P. Hejzlar, The impact of uncertainties on the performance of passive systems, Nucl. Technol. 149 (2005) 129-140.
- W. Peng, T. Chen, Q. Sun, J. Wang, S. Yu, Preliminary experiment design of graphite dust emission measurement under accident conditions for HTGR, Nucl. Eng. Des. 316 (2017) 218-227. https://doi.org/10.1016/j.nucengdes.2017.03.014
- A.A. Ryabov, V.I. Romanov, S.S. Kukanov, K.V. Tsiberev, S.V. Evropin, A.P. Rakhmanov, Numerical study of the dynamic strength of RBMK-1000 stack with fuel channel rupture, Atom. Energy (2018) 1-6.
- Z. Gao, Z. Jiang, B. Li, C. Wang, Safety analysis of accident scenarios for the HTR-10, Tsinghua Sci. Technol. 1 (1996) 27-31. https://doi.org/10.1109/TST.1996.6078139
- G. Wang, S. Niu, R. Cao, Summary of severe accident issues of LBE-cooled reactors, Ann. Nucl. Energy (2018) 531-539.
- X. Li, L.I. Shi, Z. Zhang, S. He, Safety analysis for hot gas duct vessel in HTR-PM, Nucl. Technol. 174 (2011) 29-40.
- S. Zhang, J. Tong, J. Zhao, An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment, Reliab. Eng. Syst. Saf. 155 (2016) 147-159. https://doi.org/10.1016/j.ress.2016.07.008
- Shinozuka M, Kako T, Hwang H, Reich M. Development of a Reliability-Analysis Method for Category I Structures. International Conference on Structural Mechanics in Reactor Technology. United States 1983. p. 1-8.
- F. Sanchez-Saez, A.I. Sꠑanchez, J.F. Villanueva, S. Carlos, S. Martorell, Uncertainty analysis of a large break Loss of coolant accident in a pressurized water reactor using non-parametric methods, Reliab. Eng. Syst. Saf. 174 (2018) 19-28. https://doi.org/10.1016/j.ress.2018.02.005
- F.S. D'Auria, H. Glaeser, S. Lee, J. Miak, M. Modro, R. Schultz, Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation, IAEA Safety Report Series: IAEA, 2008.
- X. Zheng, H. Itoh, H. Tamaki, M. Yu, An integrated approach to source term uncertainty and sensitivity analyses for nuclear reactor severe accidents, J. Nucl. Sci. Technol. 53 (2016) 333-344.
- J.F.E. Briesmeister, MCNP - A General Monte Carlo N-Particle Transport Code, 2003.
- W. Wang, F.D. Maio, E. Zio, Three-Loop Monte Carlo simulation approach to multi-state physics modeling for system reliability assessment, Reliab. Eng. Syst. Saf. 167 (2017) 276-289. https://doi.org/10.1016/j.ress.2017.06.003
- Y. Fukano, SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments, Ann. Nucl. Energy 77 (2015) 376-392. https://doi.org/10.1016/j.anucene.2014.11.034
- B.S. Anis, J. Areeya, H. Tewfik, J.R. White, Assessment of RELAP5 model for the university of Massachusetts lowell research reactor, Nucl. Technol. Radiat. Prot. 21 (2006) 3-12.
- R. Li, X.N. Chen, L. Andriolo, A. Rineiski, 3D numerical study of LBE-cooled fuel assembly in MYRRHA using SIMMER-IV code, Ann. Nucl. Energy 104 (2017) 42-52. https://doi.org/10.1016/j.anucene.2017.02.009
- H.P. Lee, Shell finite element of reinforced concrete for internal pressure analysis of nuclear containment building, Nucl. Eng. Des. 241 (2011) 515-525. https://doi.org/10.1016/j.nucengdes.2010.11.008
- C. Zhao, J. Chen, Numerical simulation and investigation of the base isolated NPPC building under three-directional seismic loading, Nucl. Eng. Des. 265 (2013) 484-496. https://doi.org/10.1016/j.nucengdes.2013.07.032
- J. Lubliner, J. Oliver, S. Oller, E. Onate, A plastic-damage model for concrete, Int. J. Solids Struct. 25 (1989) 299-326. https://doi.org/10.1016/0020-7683(89)90050-4
- J. Lee, G.L. Fenves, Plastic-damage model for cyclic loading of concrete structures, J. Eng. Mech. 124 (1998) 892-900.
- GB50010. Code for Design of Concrete Structures, China Architecture & Building Press, Beijing, 2010 (in Chinese).