2016 Fiscal Year Final Research Report
Simulation experiments on failure of Zircaloy cladding due to a coolant loss, and oxidation behaviors of Zircaloy at temperatures through the transition temperatures of ZrO2
Project/Area Number |
25289236
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Research Category |
Grant-in-Aid for Scientific Research (B)
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Allocation Type | Partial Multi-year Fund |
Section | 一般 |
Research Field |
Composite materials/Surface and interface engineering
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Research Institution | Akita University |
Principal Investigator |
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Co-Investigator(Kenkyū-buntansha) |
福本 倫久 秋田大学, 工学(系)研究科(研究院), 准教授 (20343064)
原 基 秋田大学, 工学(系)研究科(研究院), 教授 (50156494)
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Project Period (FY) |
2013-04-01 – 2017-03-31
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Keywords | ジルカロイ / 水蒸気酸化 / 酸素センサー / 水素センサー / 酸素ポンプセンサー |
Outline of Final Research Achievements |
At an initial stage of the Fukushima nuclear accident, a Zircaloy cladding was destroyed and a hydrogen explosion occurred. To analyze this phenomenon, a simulation experiment and a steam oxidation experiment of the Zircaloy were carried out. An electric heating wire was inserted in a Zircaloy-4 tube instead of a nuclear fuel. Using a hydrogen sensor, hydrogen generation due to a coolant loss was successfully surveyed. The oxidation behavior of the metal was investigated at high temperatures in a flowing Ar-H2O mixed gas using hydrogen and oxygen sensors. The sensor was useful for surveying hydrogen generation due to steam decomposition. The oxidation rate of the metal from generated hydrogen amount is in agreement with one measured thermogravimetrically.A change of oxidation rate was clearly detected at a monoclinic tetragonal transition temperature of ZrO2. Above results show that the gas sensing method is useful to survey oxidation process of the metal due to steam water.
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Free Research Field |
高温酸化
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