Irradiation Assisted Stress Corrosion Cracking of Reactor Internals of Light Water Reactors

轻水堆堆内构件的辐照辅助应力腐蚀开裂

• 批准号: 02044012
• 负责人: SHOJI Tetsuo
• 金额: $ 3.26万
• 依托单位: Tohoku University
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for international Scientific Research
• 财政年份: 1990
• 资助国家: 日本
• 起止时间: 1990 至 1991
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-02044012/
• 关键词: Irradiation Assisted Stress Corrosion Cracking; High Temperature Water; Grain Boundary Segregation; Cr-depletion; SSRT; Nondestructive Evaluation; Electro-chemical method; IGSCC; 照射誘起偏析; 低ひずみ速度; 不純物; 中性子照射; γ線照射

The objective of this research is to develop a nondestructive evaluation method for detection of radiation induced segregation such as Cr-depletion with very narrow width and impurities segregation. These changes in grain boundary chemistries are possible causes of Irradiation Assisted Stress Corrosion Cracking. Several heats of Type 304 Stainless Steels including high purity, commercial purity, nuclear grade, low sulfur materials. In addition to grain boundary chemical analysis, slow strain rate tests were performed in oxygenated high temperature water at 288ﾟC. Results can be summarized as follows,1. Modified EPR can detect irradiation induced narrow Cr depletion.2. RIS was strongly affected by carbon content and nuclear grade material showed the highest resistance to IGSCC.3. Impurity segregation can be quantitatively evaluated by total charge density measured at-1050mv for one hours in 5N-H_2SO_44. These NDE technique can be applied to TEM disc specimens by RIS detector.5. IGSCC region can be mapped in terms of Cr-depletion and impurity segregation.6. Further research is needed to evaluate the segregation of B and N which can transmute to form He and H and results in grain boundary weakening.Taking account of those grain boundary analysis and it relation to IGSCC, IASCC mechanisms can be made clear.

本研究的目的是开发一种无损评价方法来检测辐射引起的偏析，例如宽度非常窄的铬耗尽和杂质偏析。晶界化学的这些变化是辐照辅助应力腐蚀开裂的可能原因。几炉304型不锈钢，包括高纯度，商业纯度，核级，低硫材料。除晶界化学分析外，还在288 ℃的含氧高温水中进行了慢应变速率试验。研究结果如下：1.改进的EPR可以检测到辐照引起的窄Cr耗尽. RIS受碳含量的影响很大，核级材料对IGSCC表现出最高的抗性。在5 N-H_2SO_44介质中，在-1050mv电压下保持1h，用总电荷密度定量评价杂质偏析。这些无损检测技术可应用于透射电镜圆盘试样的RIS检测. IGSCC区域可以根据Cr的耗尽和杂质偏聚来映射. B和N的偏聚是导致晶界弱化的主要原因，结合晶界分析及其与IGSCC的关系，可以进一步明确IASCC的机理。

项目成果

Y.Watanabe;T.Shoji: "The Evaluation of In-Service Materials Degradation of Low-Allow Steels by the Electrochemical Method" Metallurgical Transactions A. 22A. 2097 (1991)

Y.Watanabe；T.Shoji：“通过电化学方法评估低合金钢在役材料的降解”Metallurgical Transactions A.22A。

Tetsuo Shoji;Satoshi Mori;Hideya Anzai;Jiro Kuniya: "Quantitative Evaluation of Stress Corrosion Crack Grack Growth Behavior on Inconel 600 in a Simulated LWR Environment" Life Prediction of Corrodible Structure,Sept.23-26,1991,Cambridge,U.K.

Tetsuo Shoji;Satoshi Mori;Hideya Anzai;Jiro Kuniya：“在模拟 LWR 环境中对 Inconel 600 上应力腐蚀裂纹裂纹生长行为的定量评估”腐蚀结构的寿命预测，1991 年 9 月 23-26 日，英国剑桥

斎藤 喜久,庄子 哲雄,渡辺 豊: "電気化学的手法によるステンレス鋼の材質劣化現位置評価技術の開発" 日本機械学会論文集(A編). 57. 164-170 (1991)

Yoshihisa Saito、Tetsuo Shoko、Yutaka Watanabe：“利用电化学方法开发不锈钢材料劣化的原位评估技术”日本机械工程师学会汇刊（编辑 A）57. 164-170 (1991)。

Y. Iwabuchi, T. Shoji, T. Fujimoto: "Research on Irradiation Assisted Stress Corrosion cracking" Proceedings of Spring Annual Meeting of Japan Society of Corrosion Engineers. (1992)

Y. Iwabuchi、T. Shoji、T. Fujimoto：“辐照辅助应力腐蚀开裂研究”日本腐蚀工程师学会春季年会论文集。

Tetsuo Shoji Satoshi Mori Hideya Anzai,jiro Kuniya: "Quantitative Evaluation of Stress Corrosion Crack Growth Behavior on Inconel 600 in a Simulated LWR Environment" Life Prediction of Corrodible Structure,Sept.23-26,1991,Cambridge,U.K.

Tetsuo Shoji Satoshi Mori Hideya Anzai，jiro Kuniya：“在模拟轻水堆环境中对 Inconel 600 应力腐蚀裂纹扩展行为的定量评估”腐蚀结构的寿命预测，1991 年 9 月 23-26 日，英国剑桥