论文部分内容阅读
9210001 轻水反应堆电站中腐蚀损坏事故及有关问题研究——石原只雄。防食技术,1990,39(11):621(英文) 报道了最近有关腐蚀事故和公用事业公司所采用的补救措施。具体为(1)BWR_s奥氏体钢管的晶间应力腐蚀开裂(IGSCC);(2)BWR_s不锈钢管焊件枝晶应力腐蚀开裂(IDSCC);(3)未敏化处理的奥氏体不锈钢堆芯组件的辐照加速应力腐蚀开裂(1ASCC);(4)PWR_s蒸汽发生器管材料的晶间腐蚀(IGA):(5)碳钢管的腐蚀疲劳和冲刷腐蚀;(6)反应堆组件的应力腐蚀开裂;(7)微生物引起的腐蚀。 (注:BWR_s——沸水堆;PWR_s——压水堆) 9210002 PWRs中锆合金燃料包壳水侧氧化的模
Corrosion Damage Occurred in Light Water Reactor Power Station and Related Problems - Only Ishihara. Anti-Fighting Techniques, 1990, 39 (11): 621 (English) Reported Recent Remedies Used in Corrosion and Utilities Companies. (1) BWR_s austenitic steel pipe intergranular stress corrosion cracking (IGSCC); (2) BWR_s stainless steel pipe weldment dendrite stress corrosion cracking (IDSCC); (3) the unsilenced austenitic stainless steel reactor (1ASCC) of the core assembly; (4) IGA of the PWR_s steam generator tube material: (5) corrosion fatigue and erosion of the carbon steel tube; (6) stress corrosion of the reactor assembly Cracking; (7) microbial-induced corrosion. (Note: BWR_s-- boiling water reactor; PWR_s-- PWR) 9210002 PWRs zirconium alloy fuel cladding water-side oxidized mold