RESEARCH ON IRRADIATION ASSISTED STRESS CORROSION CRACKING(IASCC) OF REACTOR INTERNALS

反应堆内部辐照辅助应力腐蚀开裂(IASCC)研究

• 批准号: 01044014
• 负责人: SHOJI Tetsuo
• 金额: $ 2.24万
• 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: 1989
• 资助国家: 日本
• 起止时间: 1989 至 无数据
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-01044014/
• 关键词: IRRADIATION ASSISTED STRESS CORROSION CRACKING; SENSITIZATION; GRAIN BOUNDARY SEGREGATION; Cr DEPLATION SLOW STRAIN RATE TESTS; SULFUR; PHOSPHOROUS; INTERGRANULAR CRACKING EPR; CORIOU TEST; EPR; Coriou試験

OBJECTIVES OF THIS RESEARCH ARE TO SIMULATE THE GRAIN BOUNDARY STRUCTURE AND CHEMISTRY OF IRRADIATION ASSISTED GRAIN BOUNDARY SEGREGATION BY THERMAL TREATMENTS ANF TO CHARACTERIZE THE GRAIN BOUNDARIES IN CORRELATION WITH IGSCC SUSCEPTIBILITY BY MEANS OF SSRT IN SIMULATED LWR WATER ENVIRONMENTS.IN THIS YEAR, MAIN EFFORTS HAVE BEEN PAID FOR DETERMINATION OF MATERIALS SELECTION FOR THE PURPOSE MENTIONED ABOVE AND FINALIZED 7 AUSTENITIC STAINLESS STEELS WITH A VARIATION OF IMPURITY CONTENTS.CHARACTERIZATION OF GRAIN BOUNDARY WERE PERFORMED BY EPR AND CORIOU TESTS. IGSCC WAS REPRODUCED ON THE MATERIALS WITH GRAIN BOUNDARY SEGREGATION OF SULFUR AND PHOSPHOROUS AND WITH NON SENSITIZED CONDITIONS. HIGH CRACKING SUSCEPTIBILITY WAS OBTAINED ON THE SPECIMENS WITH SEGRAGATION.

本研究的主要目的是在模拟轻水堆水环境中，用热模拟方法模拟辐照辅助晶界偏聚的晶界结构和化学过程，并用SSRT方法表征晶界与IGSCC敏感性的关系。为确定上述用途的材料选择，进行了主要努力，并最终确定了7种不同的奥氏体不锈钢杂质含量的测定。用电子顺磁共振（EPR）和科里奥利试验确定了晶界的特征。在非敏化条件下，硫、磷存在晶界偏聚的材料会产生IGSCC。在使用SEGRAPHIC的试样上获得了高的开裂敏感性。

项目成果

TETSUO SHOJI,SHIN-ICHI MORIYA AND MAKOTO TADA: "COMPUTER SIMULATION OF ENVIRONMENTALLY ASSISTED CRACKING OF RPV STEELS IN LWR ENVIRONMENTS" PROC.OF FOURTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-LIGHT WAT

TETSUO SHOJI、Shin-ichi Moriyaa 和 Makoto Tada：“轻水堆环境下 RPV 钢环境辅助裂解的计算机模拟”Proc.Of 第四届核电系统材料环境降解国际研讨会-轻水

TETSUO SHOJI,KIYOSHI KIUCHI AND TATSUO KONDO: "MATERIALS COMPATIBILITY WITH HIGH TEMPERATURE WATERS AND LONG TERM STABILITY IN NUCLEAR REACTOR ENVIRONMENTS" PROC.OF FOURTH INTERNATION SYMPOSIUM ON ENVIRONMENTAL DEGRADATION MATERIALS IN NUCLEAR POWER SYSTE

TETSUO SHOJI、KIYOSHI KIUCHI 和 TATSUO KONDO：“核反应堆环境中的材料与高温水的相容性和长期稳定性”Proc.OF 第四届国际核电系统环境降解材料研讨会

TETSUO SHOJI, KIYOSHI KIUCHI AND TATSUO KONDO: "MATERIALS COMPATIBILITY WITH HIGH TEMPERATURE WATERS AND LONG TERM STABILITY IN NUCLEAR REACTOR ENVIRONMENTS(INVITED)" PROC. OF FOURTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUC

TETSUO SHOJI、KIYOSHI KIUCHI 和 TATSUO KONDO：“核反应堆环境中的材料与高温水的相容性和长期稳定性（特邀）”

TETSUO SHOJI AND KENICHI YAMAKI: "EFFECTS OF IMPURITIES UPON IGSCC OF NON-SENSITIZED AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER" PROC. JSME SYMPOSIUM ON STRENGTH EVALUATION OF ADVANCED MATERIALS. AUGUST. (1990)

TETSUO SHOJI 和 KENICHI YAMAKI：“杂质对高温水中非敏化奥氏体不锈钢 IGSCC 的影响”PROC。

庄子哲雄,八巻健一: "非鋭敏化オ-ステナイト系ステンレス鋼の高温水中粒界応力腐食割れに及ぼす不純物の影響" 「破壊と新技術」シンポジウム,日本機械学会. 8月. (1990)

Tetsuo Shoko、Kenichi Yamamaki：“杂质对高温水中非敏化奥氏体不锈钢晶间应力腐蚀开裂的影响”“断裂与新技术”研讨会，日本机械工程师学会（1990 年）。