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On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors
Journal of Nuclear Materials ( IF 2.8 ) Pub Date : 2021-09-10 , DOI: 10.1016/j.jnucmat.2021.153265
Qian Xiao 1, 2 , Chaewon Kim 1 , Changheui Jang 1 , Chaewon Jeong 1 , Hyunmyung Kim 3 , Junjie Chen 1, 4 , Woong Heo 1
Affiliation  

A few tests were performed to evaluate the feasibility of 2205 duplex stainless steel (DSS) as an accident tolerant fuel (ATF) cladding material, including corrosion tests in simulated pressure water reactor (PWR) primary water and high-temperature steam, stress corrosion cracking (SCC) initiation test, mechanical properties test and thermal aging effects. In both 360 °C PWR primary water and 1200 °C steam, DSS 2205 showed weight changes comparable to the high-Cr alloys. After 3163 h of exposure in 400 °C steam, U-bend specimens of DSS 2205 showed no obvious cracks, suggesting that SCC is not likely to be initiated during the service life. Compared to FeCrAl alloys, DSS 2205 showed comparable strength but greater ductility. Though 400 °C thermal aging caused an increase in strength for DSS 2205, total elongation was more than 35% even after 11,061 h aging, greater than other Fe-based ATF alloys. Also, concerns on neutron penalty, irradiation, fabrication and spent fuel storage were discussed. The overall results suggest that DSS 2205 could be considered as a candidate ATF cladding material.



中文翻译:

双相不锈钢2205作为轻水反应堆容灾燃料包壳材料的可行性

进行了一些测试以评估 2205 双相不锈钢 (DSS) 作为事故容错燃料 (ATF) 包壳材料的可行性,包括在模拟压力水反应堆 (PWR) 一次水和高温蒸汽中的腐蚀测试、应力腐蚀开裂(SCC) 起爆试验、机械性能试验和热老化效应。在 360 °C PWR 一次水和 1200 °C 蒸汽中,DSS 2205 的重量变化与高铬合金相当。在 400°C 蒸汽中暴露 3163 小时后,DSS 2205 的 U 形弯曲试样没有出现明显的裂纹,表明在使用寿命期间不太可能发生 SCC。与 FeCrAl 合金相比,DSS 2205 表现出可比的强度但更好的延展性。尽管 400 °C 的热老化导致 DSS 2205 的强度增加,但即使经过 11 年,总伸长率仍超过 35%,061 h 时效,大于其他铁基 ATF 合金。此外,还讨论了对中子惩罚、辐照、制造和乏燃料储存的关注。总体结果表明,DSS 2205 可被视为候选 ATF 包覆材料。

更新日期:2021-09-12
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