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一种基于混合传导模型的一回路结构材料腐蚀-活化-迁移模型及其应用 被引量:2

A Model for Zinc Addition Effect on Corrosion Product Release,Activation and Transportation in RCS Based on Mixed-conduction Model and Its Application
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摘要 为了定量分析反应堆冷却剂加锌工艺对一回路系统堆芯外放射性水平的影响,本文结合描述材料微观腐蚀过程的混合传导模型(MCM)和描述腐蚀产物活化、迁移及沉积的宏观输运模型,形成了能够系统性描述一回路结构材料腐蚀-活化-迁移的联合模型,并通过遗传算法分析及文献调研确定模型各主要参数。经校验表明该模型能够有效计算正常运行工况下一回路中结构材料的均匀腐蚀程度,同时也能给出结构材料表面沉积层的放射性活度分布。使用该模型对加锌前后系统内不同分区的活度分别进行了计算,结果表明加锌工艺能显著降低一回路堆芯外放射性水平。 The mixed-conduction model (MCM) was used to characterize the microscopiccorrosion process of primary structure materials. The results combined with themacroscopic transporting model characterizing the activation, migration and depositionprocesses of corrosion products was investigated in order to study the effect of reactorcoolant zinc application on the radiation field reduction expectations in the reactorcoolant system (RCS). A combined model was established which could quantitativelydepict those processes and the pivotal parameters of the model were obtained through genetic algorithm analysis and literature studies. Then the model's algorithm was calibrated and showed that it could effectively calculate the effect of zinc addition on activation, migration and deposition processes of corrosion products and could also carry out radioactivity distribution for the primary side. The radioactivity of different regions of RCS was also calculated using this model. The results showed that zinc addition strategy could significantly reduce the radiation field for out-of-core region.
出处 《核科学与工程》 CSCD 北大核心 2017年第2期169-175,共7页 Nuclear Science and Engineering
基金 大型先进压水堆核电站国家重大科技专项
关键词 加锌 腐蚀 迁移 放射性活度 Zinc addition Corrosion Migration Radioactivit
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  • 1STELLWAG B.The mechanism of oxide filmformation on austenitic stainless steels in hightemperature water[J].Corrosion Science,1998,40(2-3):337-370.
  • 2MACHET A,GALTAYRIES A,MARCUS P,et al.XPS study of oxides formed on nickel-basealloys in high-temperature and high-pressure wa-ter[J].Surf Interface Anal,2002,34(1):197-200.
  • 3O’NEILL H S C.Temperature dependence ofthe cation distribution in zinc ferrite(ZnFe2O4)from powder XRD structural refinements[J].European Journal of Mineralogy,1992,4(3):571-580.
  • 4LISTER D H.Activity transport and corrosionprocesses in PWRs[J].Nuclear Energy,1993,32(2):103-114.
  • 5Burke M A. Materials selection and validation for light water reactor electricity generating capacity sustainabil- ity[A], 5th IMR Symposium on Materials Science and Engineering: Materials and Reliability in Nuclear Power Plants[C]. China, Shenyang: 2009.
  • 6Nakagawa T, Totsuka N, Terachi T, et al. Influence of dis- solved hydrogen on oxide film and PWSCC of Alloy 600 in PWR primary water[J]. J. Nucl. Sci. Technol., 2003, 40(1): 39-43.
  • 7Terachi T, Fujii K, Arioka K. Microstructure characteriza- tion of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320 ℃ [J]. J. Nucl. Sci. Technol., 2003, 42(2): 225-232.
  • 8Tostuka N, Szklarska-Smialowska Z. Hydrogen induced IGSCC of two unsensitized austenitic stainless steels in high-temperature water[J]. Corrosion, 1988, 44(2): 124- 126.
  • 9Arioka K. Effect of temperature hydrogen and boric acid concentration on IGSCC susceptibility of annealed 316 stainless steel[A]. Proc. Int. Symp. Fontevraud 5[C]. 2002:23-27.
  • 10Arioka K, Yamada T, Takumi T. Influence of boric acid, hydrogen concentration and grain boundary carbide on IGSCC behaviors of SUS 316 under PER primary wa- ter[A]. Proc. llth Int. Conf. Environmental Degrada- tion of Materials in Nuclear Systems [C]. Stevenson, 2003: 10-14.

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