共 27 条
- [1] Zinkle S.J., Was G.S., Materials challenges in nuclear energy[J], Acta Materialia, 61, 3, pp. 735-758, (2013)
- [2] Cheng Ren-Shan Y.A.O.L., Wu L., Et al., Compara-tive study on the temperature rise of the cladding material during induction and resistance heating under LOCA condition[J]. Packaging, Engineering, 41, 9, pp. 91-99, (2020)
- [3] Volchek A., Zvonarev Y., Schanz G., Et al., Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations: PART II. Best-fitted parabolic correlations[J], Nuclear Engineering and Design, 232, 1, pp. 85-96, (2004)
- [4] Terrani K A., Pint B A., Parish C M., Et al., Silicon carbide oxidation in steam up to 2 MPa[J], Journal of the American Ceramic Society, 97, 8, pp. 2331-2352, (2014)
- [5] Deng Y., Shirvan K., Wu Y., Et al., Probabilistic view of SiC/SiC composite cladding failure based on full core the-rmo-mechanical response[J], Journal of Nuclear Materials, 507, pp. 24-37, (2018)
- [6] Singh G., Terrani K., Katoh Y., Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis[J], Journal of Nuclear Materials, 499, pp. 126-143, (2018)
- [7] Pint B.A., Performance of FeCrAl for accident fuel cladd-ing in high temperature steam[J], Corrrosion Reviews, 35, 3, pp. 167-175, (2017)
- [8] Wang D., Xie F., Li X., Et al., Effective of interfacial film on the corrosion behaviour of X80 pipeline steel in a neutral soil environment containing sulphate-reducing bacteria[J], Corrosion Reviews, 35, 6, pp. 445-453, (2017)
- [9] Tang C., Stueber M., Seifert H.-J., Et al., Protective coatings on zirconium-based alloys as accident-tolerant fuel(ATF) claddings[J], Corrosion Reviews, 35, 3, pp. 141-165, (2017)
- [10] Kim H G., Kim I H., Park J Y., Et al., Application of Coating Technology on Zirconium-Based Alloy to Decrease High-Temperature Oxidation[C]//17Th International Symposium, (2014)