Corrosion Control for Internal Structure of Nuclear Reactor Based on Radiation Induced Surface Activation Phenomenon

基于辐射诱导表面活化现象的核反应堆内部结构腐蚀控制

基本信息

项目摘要

When a semiconductor film is irradiated by γ-ray, excited electrons are transferred to a base metal in contact with the film, resulting in a drop of corrosion potential. This study proposes a corrosion mitigation method based on radiation induced surface activation(RISA) phenomena by supplying γ-rays from outside the material, or based on a self-excited methodology activating the film and/or the base metal. The results of the study revealed that electrons in the oxide film were activated by γ-ray irradiation and transferred from the oxide to the adjacent base metal. This made the corrosion potential of the metal less noble through a process in which the radiation induced a surface activation phenomenon, even in Zirconium oxide (ZrO_2) films which had large band gap energies. The mitigating method for the corrosion of metals was developed by utilizing this effect. The method involved external γ-rays irradiation introduced by activation of oxide films and/or base metals corrosion potential of ZrO_2 coated SUS304L was shifted down to the range between 90 mV and 300 mV vs. SSE by γ-ray irradiation. The corrosion potential was further shifted down to 600 mV when a CoCr intermediate layer was inserted between the ZrO_2 spray coating film and the SUS304L base metal. Iron specimens with a spray coating film of TiO_2,ZrO_2, and Al_2O_3 were immersed in a 3 wt% sodium chloride aqueous solution. Pitting and general corrosion were suppressed on all three specimens irradiated with γ-rays.These results clearly show that the corrosion potential of stainless steel could be less noble up to a level of -600 mV vs. SSE with this methodology and these processes would have a remarkable effect in mitigating the corrosion of stainless steels used in internal structures of nuclear reactors.
当用γ射线照射半导体膜时,激发的电子转移到与膜接触的基底金属,导致腐蚀电位下降。本研究提出了一种基于辐射诱导表面活化(RISA)现象的腐蚀缓解方法,通过从材料外部提供γ射线,或基于自激方法活化膜和/或基体金属。研究结果表明,氧化膜中的电子被γ射线激活,并从氧化物转移到相邻的基体金属。这使得金属的腐蚀电位通过辐射诱导表面活化现象的过程而降低,即使在具有大带隙能量的氧化锆(ZrO_2)膜中也是如此。利用这一效应,开发了金属腐蚀的减缓方法。该方法通过引入γ射线激活氧化膜和/或基体金属,使ZrO_2涂层的SUS 304 L的腐蚀电位下降到90 ~ 300 mV。当在ZrO_2喷涂层与SUS 304 L基体之间插入CoCr中间层时,腐蚀电位进一步下降到600 mV。将喷涂有TiO_2,ZrO_2和Al_2O_3涂层的铁试样浸泡在3wt%的氯化钠水溶液中。这些结果清楚地表明,采用这种方法,不锈钢的腐蚀电位可以降低到-600 mV vs. SSE的水平,这些过程将对减轻核反应堆内部结构中使用的不锈钢的腐蚀具有显着的效果。

项目成果

期刊论文数量(40)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
放射線誘起表面活性によるセラミック被覆材の腐食電位低下
由于辐射引起的表面活性,陶瓷涂层的腐蚀电位降低
藤沢匡介, 師岡慎一, 菱田護, 古谷正裕, 植松進, 中村秀夫, 三島嘉一郎, 関村直人, 岡本孝司, 賞雅寛而: "放射線誘起表面活性効果による高性能原子炉に関する技術開発(1)-全体計画-"日本原子力学会2004年春の年会要旨集. 第II分冊. 287 (2004)
Keisuke Fujisawa、Shinichi Shioka、Mamoru Hishida、Mamoru Furuya、Susumu Uematsu、Hideo Nakamura、Kaichiro Mishima、Naoto Sekimura、Takashi Okamoto、Hiroshi Shomasa:“利用辐射诱导表面活性效应的高性能核反应堆的技术开发 (1) -总体计划-《日本原子能学会2004年春季年会摘要》.卷II.287(2004)
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Innovative Nuclear Technologies Based on Radiation Induced Surface Activation(RISA) (3)Durability and Mechanical Properties of Spray Coatings
基于辐射诱导表面活化(RISA)的创新核技术(3)喷涂层的耐久性和机械性能
賞雅 寛而, 岡本 孝司, 三島 嘉一郎, 古谷 正裕: "放射線誘起表面活性現象の発見とその利用"日本原子力産業会議放射線利用研究会3グループ合同研究会照射利用グループ講演資料. 25-45 (2003)
Hiroshi Shoma、Takashi Okamoto、Kaichiro Mishima、Masahiro Furuya:“辐射引起的表面活性现象的发现及其利用”日本原子能工业委员会辐射应用研究组联合研究组辐射应用组演示材料25-45(2003)。
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Corrosion Control on the Basis of Radiation Induced Surface Activation
基于辐射诱导表面活化的腐蚀控制
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