Citation: | Jia Yuzhen, Qiu Jun, Cheng Zhuqing, Yang Zhongbo. Effect of Final Annealing Temperature on Microstructure and Properties of N36 Alloy Tube[J]. Nuclear Power Engineering, 2023, 44(S1): 163-167. doi: 10.13832/j.jnpe.2023.S1.0163 |
[1] |
SABOL G, COMSTOCK R J, WEINER R A, et al. In-reactor corrosion performance of ZIRLO and zircaloy-4[C]//Zirconium in the Nuclear Industry: Tenth International Symposium. Philadelphia: ASTM International, 1994: 724-743.
|
[2] |
NOVIKOV V V, MARKELOV V A, TSELISHCHEV A V, et al. Structure-phase changes and corrosion behavior of E110 and E635 claddings of fuels in water cooled reactors[J]. Journal of Nuclear Science and Technology, 2006, 43(9): 991-997. doi: 10.1080/18811248.2006.9711187
|
[3] |
JEONG Y H, PARK S Y, LEE M H, et al. Out-of-pile and in-pile perfomance of advanced zirconium alloys (HANA) for high burn-up fuel[J]. Journal of Nuclear Science and Technology, 2006, 43(9): 977-983. doi: 10.1080/18811248.2006.9711185
|
[4] |
赵文金,周邦新,苗志,等. 我国高性能锆合金的发展[J]. 原子能科学技术,2005, 39(S1): 2-9.
|
[5] |
ANADA H, NOMOTO K, SHIDA Y. Corrosion behavior of zircaloy-4 sheets produced under various hot-rolling and annealing conditions[C]//Zirconium in the Nuclear Industry: Tenth International Symposium. Philadelphia: ASTM International, 1994: 307-327.
|
[6] |
GARDE A M. Enhancement of aqueous corrosion of zircaloy-4 due to hydride precipitation at the metal-oxide interface[C]//Zirconium in the Nuclear Industry: Ninth International Symposium. Philadelphia: ASTM International, 1991: 566-591.
|
[7] |
SCHEMEL J J, CHARQUET D, WADIER J F. Influence of the manufacturing process on the corrosion resistance of zircaloy-4 cladding[C]//Zirconium in the Nuclear Industry: Eighth International Symposium. Philadelphia: ASTM International, 1989: 141-152.
|
[8] |
RUDLING P, PETTERSSON H, ANDERSSON T, et al. Corrosion performance of zircaloy-2 and zircaloy-4 PWR fuel cladding[C]//Zirconium in the Nuclear Industry: Eighth International Symposium. Philadelphia: ASTM International, 1989: 213-226.
|
[9] |
YANG Z B, LIAO J J, QIU S Y, et al. Effect of final annealing temperature on corrosion resistance of sza-6 zirconium alloy cladding tubes[J]. Materials Science Forum, 2019, 944: 488-498. doi: 10.4028/www.scientific.net/MSF.944.488
|
[10] |
PARK J Y, JEONG Y H, JUNG Y H. Effects of precipitation characteristics on the out-of-pile corrosion behavior of niobium-containing zirconium alloys[J]. Metals and Materials International, 2001, 7(5): 447-455. doi: 10.1007/BF03027086
|
[11] |
BAEK J H, JEONG Y H, KIM I S. Effects of the accumulated annealing parameter on the corrosion characteristics of a Zr-0.5Nb-1.0Sn-0.5Fe-0.25Cr alloy[J]. Journal of Nuclear Materials, 2000, 280(2): 235-245. doi: 10.1016/S0022-3115(99)00288-3
|
[12] |
MARDON J P, CHARQUET D, SENEVAT J. et al. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy[C]//Zirconium in the Nuclear Industry: Twelfth International Symposium. West Conshohocken: ASTM International, 2000: 505-524.
|