IS ZIRCONIUM OXIDE MORPHOLOGY ON FUEL CLADDING LARGELY DETERMINED BY LITHIUM HYDROXIDE CONCENTRATION EFFECTS

Cox B.

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IS ZIRCONIUM OXIDE MORPHOLOGY ON FUEL CLADDING LARGELY DETERMINED BY LITHIUM HYDROXIDE CONCENTRATION EFFECTS

机译：氢氧化锂浓度效应大幅度测定的燃料熔覆上氧化锆的形貌

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The oxide morphology of films on fuel cladding undergoing enhanced corrosion in BR3 is compared with laboratory observations of degradation of zirconium oxide films in concentrated LiOH solutions. It is concluded that such an LiOH concentration process could have caused the enhanced corrosion in BR3. This probably was initiated by crud deposition raising the surface temperature of the cladding above the saturation temperature during the first cycle of operation in BR3. (C) 1997 Elsevier Science B.V. [References: 22]

机译：将燃料包壳中BR3腐蚀加剧的薄膜的氧化物形态与浓LiOH溶液中氧化锆薄膜降解的实验室观察结果进行了比较。结论是，这种LiOH浓缩过程可能导致BR3腐蚀增强。这可能是由于在BR3的第一个操作周期中，粗屑沉积使包层的表面温度升高到高于饱和温度而引发的。（C）1997 Elsevier Science B.V. [参考：22]

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《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |1997年第1期|共4页
作者
Cox B.;
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正文语种 eng
中图分类原子能技术;
关键词
In-reactor; Zircaloy-4; Autoclave; Evolution; Impact; Layer;

机译：反应器内;Zircaloy-4;高压釜;演变;冲击;层;

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1. IS ZIRCONIUM OXIDE MORPHOLOGY ON FUEL CLADDING LARGELY DETERMINED BY LITHIUM HYDROXIDE CONCENTRATION EFFECTS [J] . Cox B. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 1997,第1期

机译：氢氧化锂浓度效应大幅度测定的燃料熔覆上氧化锆的形貌
2. Thermochemical Embrittlement of the Zirconium Cladding of a Fuel Rod and Oxidative Recrystallization of the Fuel Material in the Course of Spent Nuclear Fuel Reprocessing [J] . M. M. Metalidi, S. V. Shapovalov, R. V. Ismailov, Radiochemistry . 2015,第1期

机译：乏核燃料后处理过程中燃料棒锆覆层的热化学脆化和燃料材料的氧化重结晶
3. Porosity in oxides on zirconium fuel cladding alloys, and its importance in controlling oxidation rates [J] . N. Ni, S. Lozano-Perez, M.L. Jenkins Scripta materialia . 2010,第8期

机译：锆燃料熔覆合金氧化物的孔隙率及其在控制氧化速率中的重要性
4. ZIRCONIUM DIOXIDE AS A PROTECTIVE LAYER OF ZIRCONIUM FUEL CLADDING [C] . Barbora Benesova, Radek Skoda International conference on nuclear engineering . 2014

机译：二氧化锆作为氧化锆熔覆层的保护层
5. Anionic synthesis of highly isotactic polystyrene in the presence of lithium hydroxides or lithium alkoxides, and, Controlled "living" emulsion polymerization of methyl methacrylate by atom transfer radical polymerization. [D] . Makino, Takayuki. 1997

机译：在氢氧化锂或烷氧基锂的存在下阴离子合成高度全同立构的聚苯乙烯，以及通过原子转移自由基聚合进行甲基丙烯酸甲酯的受控“活”乳液聚合。
6. A Comparison Between the Late Effects of Thorotrast and a Non-Radioactive Zirconium Hydroxide Sol in Mice [O] . J. P. M. Bensted, J. O. Crookall 1963

机译：胸腺嘧啶和非放射性氢氧化锆溶胶对小鼠后期影响的比较
7. Irradiation effects on zirconium-clad uranium-zirconium fuel plates / [O] . Bailey, R. E., Argonne National Laboratory., ANL., 1958

机译：锆包覆铀 - 锆燃料板的辐照效应/
8. Growth kinetics for the precipitation of zirconium hydroxide from aqueous zirconium and tin bearing solutions by the addition of ammonium hydroxide [R] . Carleson, TE, Chipman, NA 1989

机译：通过添加氢氧化铵从含水锆和锡的水溶液中沉淀氢氧化锆的生长动力学

IS ZIRCONIUM OXIDE MORPHOLOGY ON FUEL CLADDING LARGELY DETERMINED BY LITHIUM HYDROXIDE CONCENTRATION EFFECTS

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