[1] Duan Z G, Yang H L, Satoh Y et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors[J]. Nuclear Engineering and Design, 316, 131-150(2017).

[2] Du C J, Hu X G, Guo P Y et al. Effect of Gd on neutron absorption properties and electrochemical corrosion behavior of Zr-Gd alloy in boiling concentrated HNO3[J]. Nuclear Science and Techniques, 34, 36(2023).

[3] Fidleris V. The irradiation creep and growth phenomena[J]. Journal of Nuclear Materials, 159, 22-42(1988).

[4] Adamson R B, Coleman C E, Griffiths M. Irradiation creep and growth of zirconium alloys: a critical review[J]. Journal of Nuclear Materials, 521, 167-244(2019).

[5] Montgomery R, Tomé C, Liu W F et al. Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis[J]. Journal of Computational Physics, 328, 278-300(2017).

[6] WANG Huacai, YANG Dawei, CHENG Huanlin et al. Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor[J]. Nuclear Techniques, 46, 090602(2023).

[7] MA Yan, ZHANG Zhixin, CHEN Jiawei. Simulation method for secondary hydriding breakage of zirconium alloy cladding[J]. Nuclear Techniques, 45, 040602(2022).

[8] ZHOU Wei. Study on low-dose neutron irradiation hardening and formation mechanisms for large defect clusters in Zr[D](2019).

[9] Bossis P, Verhaeghe B, Doriot S et al. In PWR comprehensive study of high burn-up corrosion and growth behavior of M5® and recrystallized low-tin zircaloy-4[J]. Journal of ASTM International, 6, 1-27(2009).

[10] Rogerson A. Irradiation growth in zirconium and its alloys[J]. Journal of Nuclear Materials, 159, 43-61(1988).

[11] Carpenter G J C, Zee R H, Rogerson A. Irradiation growth of zirconium single crystals: a review[J]. Journal of Nuclear Materials, 159, 86-100(1988).

[12] Yagnik S, Adamson R, Kobylyansky G et al. Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants[C], 748-795(2018).

[13] Holt R A, Causey A R, Christodoulou N et al. Non-linear irradiation growth of cold-worked Zircaloy-2[C], 1295, 623-637(1996).

[14] MA Huitong, LIU Guisen, CUI Yanguang et al. Research progress in macro-mesoscopic model of irradiation creep and growth of zirconium alloy[J]. Atomic Energy Science and Technology, 55, 108-120(2021).

[15] Patra A, Tomé C N, Golubov S I. Crystal plasticity modeling of irradiation growth in Zircaloy-2[J]. Philosophical Magazine, 97, 2018-2051(2017).

[16] Wen W, Capolungo L, Patra A et al. A physics-based crystallographic modeling framework for describing the thermal creep behavior of Fe-Cr alloys[J]. Metallurgical and Materials Transactions A, 48, 2603-2617(2017).

[17] Wen W, Capolungo L, Tomé C N. Mechanism-based modeling of solute strengthening: application to thermal creep in Zr alloy[J]. International Journal of Plasticity, 106, 88-106(2018).

[18] Wen W, Kohnert A, Arul Kumar M et al. Mechanism-based modeling of thermal and irradiation creep behavior: an application to ferritic/martensitic HT9 steel[J]. International Journal of Plasticity, 126, 102633(2020).

[19] JIAO Hao, YANG Jifeng, WANG Peinuan et al. Research on data-driven operation mechanism of dynamic capabilities—based on analysis of digital transformation process from the data lifecycle management[J]. China Industrial Economics, 174-192(2021).

[20] Soniak A, L'Hullier N, Mardon J P et al. Irradiation creep behavior of Zr-base alloys[C], 837-862(2009).

[21] LIU Shougen. Preliminary study on the present situation and development direction of database management system[J]. Nei Jiang Science Technology, 27, 20(2006).

[22] Kuang W W, Huang J, Liu G S et al. Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes[J]. Journal of Nuclear Materials, 564, 153708(2022).

[23] Lebensohn R A, Tomé C N. A self-consistent anisotropic approach for the simulation of plastic deformation and texture development of polycrystals: application to zirconium alloys[J]. Acta Metallurgica et Materialia, 41, 2611-2624(1993).

[24] Eshelby J D. The determination of the elastic field of an ellipsoidal inclusion, and related problems[J]. Proceedings of the Royal Society of London Series A, 241, 376-396(1957).

[25] Sivaraj R, Ravichandran T. A review of selection methods in genetic algorithm[J]. International Journal of Engineering Science and Technology, 3, 3792-3797(2011).

[26] Causey A R, Holt R A, Christodoulou N et al. Irradiation-enhanced deformation of Zr-2.5Nb tubes at high neutron fluences[J]. ASTM Special Technical Publication, 1354, 74-85(2000).

[27] Walters L, Bickel G, Griffiths M. The effects of microstructure and operating conditions on irradiation creep of Zr-2.5Nb pressure tubing[C], 693-725(2014).

[28] Gong J C, Benjamin Britton T, Cuddihy M A et al. 〈a〉Prismatic,〈a〉basal, and〈c+a〉slip strengths of commercially pure Zr by micro-cantilever tests[J]. Acta Materialia, 96, 249-257(2015).