晶间腐蚀
腐蚀
沸腾
材料科学
冶金
渗透(战争)
硝酸
蒸发器
传热
复合材料
化学
热力学
热交换器
工程类
物理
有机化学
运筹学
作者
Fumiyoshi Ueno,Chiaki Kato,Takafumi Motooka,Shiro Ichikawa,Masahiro Yamamoto
摘要
Abstract To evaluate the component life in a spent nuclear fuel reprocessing plant, a large-scale mock-up test apparatus of a reduced pressurized thermosiphon evaporator was constructed, and the corrosion mechanism of a heat transfer tube made of ultralow carbon type 304 stainless steel in boiling nitric acid solution was studied. The corrosion tests were conducted for about 36,000 h, and changes in the corrosion amount and rate in the test duration were discussed. The relationships between the amount of corrosion and tube surface temperature and heat flux were investigated, and the corrosion propagation mechanism considering intergranular penetration was studied based on the observations of morphologies of corrosion surfaces and the measurements of intergranular penetration depths. After a long duration, the increases in the corrosion amount and rate saturated when intergranular penetration and grain dropping occurred by turns. This result means that a linear estimation can be applied to the life prediction for corrosion. Three portions of the tube were observed, and the amounts of corrosion were different among the three portions, but no difference in the morphology of intergranular corrosion existed. The amount of corrosion was affected by both tube surface temperature and heat flux. A large amount of corrosion could be observed in both the boiling starting portion and the top, where high tube surface temperature and heat flux were observed. KEYWORDS: nuclear fuel reprocessingevaporatorintergranular corrosionlife predictionultralow carbon type 304 stainless steelheat exchanger tubemock-up testnitric acidboilingheat transferheat flux
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